NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECT · CMP, Milestone R048, for issue once the...

U.S. DEPARTMENT OF ENERGY

Nevada ;Nuclear

WasteStorage

InvestigationsPROJECT

i

OGR

NEVADA NUCLEAR WASTESTORAGE INVESTIGATIONS

PROJECT

Monthly Report

JULY 1986

WM-11 PDR

UNITED STATES DEPARTMENT OF EN ERGY

A

NEVADA OPERATIONS OFFICE

NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECT

MONTHLY REPORT

JULY 1986

Prepared by Nevada Nuclear Waste Storage Investigations (NNWSI)Project participants as part of the Civilian Radioactive WasteManagement Program. The NNWSI Project is managed by the WasteManagement Project Office of the U.S. Department of Energy (DOE),Nevada Operations Office. NNWSI Project work is sponsored by the DOEOffice of Civilian Radioactive Waste Management.

UNITED STATES DEPARTMENT OF ENERGYNEVADA OPERATIONS OFFICE

TABLE OF CONTENTS

Abstract

Key Activities ..

Funding Overview . . . . . . .

NNWSI Project Cost vs. Plan Graph . . . . . . . . . . . . . . . iv

NNWSI Project Budget Baseline .

Project Status

WBS 1.2.1 Systems .

WBS 1.2.2 Waste Package . . . . . . . . . . . . . . . . . . . . 2-1

WBS 1.2.3 Site Investigations . . . . .

WBS 1.2.4 Repository Investigations . . . . . . . . . . . . . . 4-1

WBS 1.2.5 Regulatory and Institutional Investigations . . . . . 5-1

WBS 1.2.6 Exploratory Shaft Investigations. . . . . . . . . . . 6-1

WBS 1.2.7 Test Facilities . . . . . . . . . . . . . . . . . . . 7-1

WBS 1.2.8 Land Acquisition ........ . .

WBS 1.2.9 Program Management. . . . . . . . . . . . . . . . . . 9-1

Cost Performance Report - Level 3 .

Cost Performance Report - Level 4 .

NNWSI Project Participant Budget vs. Cost. . . . . . . . . . . . . . . . 10-4

NNWSI Project Level I Milestones . . . . . . .

NNWSI Project Staffing . . . . . . . . . . . . . . . . . . . . . . . . 10-23

Planned NNWSI Project Field Activities . 10-24

ABSTRACT

Key Activities

WBS 1.2.1 Systems

Project personnel devoted major efforts for most of these tasks to preparationof work plans and quality assurance level assignments that were forwarded tothe Waste Management Project Office (WMPO) for approval. Updated costestimates for the tuff repository emplacement containers and monitoredretrievable storage containers will be used in cost estimates for requiredstudies. Printing of the report Preliminary Estimates of Groundwater TravelTime and Radionuclide Transport at Yucca Mountain Repository Site" is inprogress.

WBS 1.2.2 Waste Package

Major efforts of Project participants were concentrated on the implications andrequirements of the stop-work order and on the Site Characterization Plan(SCP).

WBS 1.2.3 Site Investigations

The stop-work orders remained in effect and almost all site chracterizationtechnical activities continued to be suspended. Scientific investigationplanning documentation and quality assurance level assignments were submittedto WMPO for approval. The problem of dating the basalt from the Lathrop Wellscone will be approached by high precision K-Ar dating, cation-ratio rockvarnish dating, and U-series dating. A two-dimensional model will be used tosimulate the effect of pumping in western Jackass Flats on the Nevada TestSite. Experiments conclusively indicate that bacteria are mobile in CalicoHills tuff. Conclusions of a report on the lateral continuity andprobabilistic models in sorptive mineral zones underlying Yucca Mountain(Milestone M331) indicate that a functional stratigraphy based on vitric,devitrified, and zeolitized rock types is valid from a mineralogic standpointas well as from a thermomechanical approach. The High-Level Nuclear WasteTransport and Storage Assessment of Potential Impacts on Tourism in the LasVegas Area" report was published. Two reports in review are PetrographicVariation of the Topopah Spring Tuff, Matrix Within and Between Core DrillHoles, Yucca Mountain, Nevada" (Milestone R320) and Lateral Continuity andProbabilistic Models in Sorptive Mineral Underlying Yucca Mountain, Nevada"(Milestone M331).

WBS 1.2.4 Repository Investigations

Approximately 17 interface control drawings will establish and control designboundaries and interfacing design features between NNWSI Project designorganizations. Preparation of SCP chapters, work plans, and quality assurancelevel assignments received the most effort. The stop-work order for the weldedtuff mining evaluations and the equipment engineering task was lifted. The

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boring machine design was found- to be complete and workable. Severalparticipants placed contracts and prepared outlines for projects related tosite facilities.

WBS 1.2.5 Regulatory and Institutional Investigations

The NNWSI Project Regulatory Document Manual" is in final production forcontrolled distribution. Efforts to procure the equipment for the InformationManagement System Bridge Program were initiated. Permanent Internal ReviewCommittees will review various sections of the SCP. Project participantsconcentrated efforts on completing various sections of the SCP. Initialplanning for the environmental impact statement is underway.

WBS 1.2.6 Exploratory Shaft Investigations

The subsystem design requirements document, delivered to WMPO contains thecriteria to be followed by the architects and engineers in the design of theexploratory shaft facility. Efforts continued to be concentrated on preparingstudy plans, procedures, and quality assurance level assignments.

WBS 1.2.7 Test Facilities

Project personnel continued to deactivate, disassemble, decontaminate, andperform final inspections of equipment and facilities at E-MAD. Effortscontinue to review and verify quality records, which are then shipped to therecords library.

WBS 1.2.9 Project Management

Review of the draft Project Management Plan was to be completed by July 30.The Project 1986 fiscal year budget is estimated to vary by 1.8 million belowthe proposed budget. The quality assurance plan for the Technical andManagement Support Services contractor was submitted to WMPO. The ualityassurance records management system is installed and operational at allparticipating organizations. Activities under this task included support forpreparation of quality level assignments, work plans, and procedures.

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JULY 1986

Funding Overview

The month-end estimated costs were 8,735,214 against a plan

resulting in a cost underrun of 2,385,616.of 11,120,830

The following are the year-to-date plans, costs, and variances:

Plan($000)

$ 5,423WBS 1.2.1 Systems

WBS

WBS

WBS

1.2.2

1.2.3

1.2.4

WBS 1.2.5

WBS 1.2.6

Waste Package

Site

RepositoryInvestigations

Regulatory andInstitutionalInvestigations

Exploratory ShaftInvestigations

Test Facilities

Project Management

NNWSI Project

5,682

26,701

11,236

10,335

9,695

883

13,995

$83,950

Cost($OOO)

$ 4,733

5,381

21,320

8,836

7,991

8,285

831

13,380

$70,757

Variance

$ 690

301

5,381

2,400

2,344

1,410

52

615

$13,193

Variance

13

5

20

21

23

15

6

4

16

WBS

WBS

1.2.7

1.2.9

WBS 1.2

iii

COSTNNWSI PROJECT

PERFORMANCE GRAPH FORWBS: 1.2

JUL 1 86

Remarks: Since approximately 80% of the Project s planned as level of effort, mostof the cost variance is derived from scheduled work not being accomplished. The costunderruns are due to stop-work orders, billing lags, and difficulty with fillingtechnical staff positions requiring specialized skills.

iv

NNWSI PROJECT BUDGET BASELINE

JULY 1986

CONTRACTORS

SNL

LLNL

Los Alamos

v

U.S. Department OF ENERGY

PROJECT STATUS

1.2.1 SYSTEMS

OBJECTIVE

The objective of this task is to apply the concept of systems to thedevelopment and design of the repository, both the surface and subsurfacefacilities, and to the evaluation of the effectiveness of the geologic andhydrologic environment in isolating radionuclides.

ACTIVITIES

WBS 1.2.1.1 SYSTEM MANAGEMENT AND INTEGRATION

During July 186 at Sandia National Laboratories (SNL) modified work plans andquality assurance level assignment sheets were completed for the systemsmanagement and integration task and forwarded to the Waste Management ProjectOffice (WMPO) for review.

WBS 1.2.1.2 SYSTEMS ENGINEERING

WBS 1.2.1.2.1 System Description

Policy-review comments on the system requirements (SR) document (MilestoneM120) were received at SNL from the WMP0 in June 1986. Revision of the SRdocument will start after completion of the draft NNWSI Project SystemEngineering Management Plan (SEMP).

Modified work plans and quality assurance level assignment sheets werecompleted at SNL for the system description task and forwarded to WMPO forreview.

The first draft of the system description (SD) document (SNL Milestone M261) isabout 80 percent complete.

WBS 1.2.1.2.2 System Studies

Identification of system studies will result from the Site CharacterizationPlan (SCP) issues-resolution process currently underway within the NNWSIProject. Further system studies will be identified as the scope of theAdvanced Conceptual Design is defined.

WBS 1.2.1.2.3 Cost Schedule

Cost estimates for the tuff repository emplacement containers and monitoredretrievable storage canisters were updated at SNL for use in cost estimates forthe Repository Conceptual Design in Support of Site Characterization (RCD/SC)and the Fuel Rod Consolidation Study. The container estimates are up slightlyfrom the February 1986 estimate, even though both are of the same design andare based upon requests for quotations received during August 1985.

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A preliminary but separate cost estimate, current as of August 1, 1986, of thesurface and underground facilities has been completed but not compiled for theRCD/SC.

WBS 1.2.1.2.4 Systems Engineering Integration

Members of the SAIC systems engineering staff submitted comments to WMPO onRadiation Dose Analysis in a Hypothetical Reference Transportation System forCommercial Spent Fuel.

A draft of the revised SEMP was sent for author review on July 21. A workshopfor authors of this revised draft was scheduled for July 29-31, 1986, atLawrence Livermore National Laboratory (LLNL). The entire draft was reviewedsection by section. Assignments were made for rewriting those parts of theplan needing revisions.

WBS 1.2.1.2.5 Configuration Management and Change Control

No comments were received from WMPO on the Draft Configuration Management Plan(CMP), SAIC Milestone R046, which was submitted for review on May 29, 1986.Review comments are required to complete the final CMP, SAIC Milestone R047,which was scheduled for completion on June 15, 1986.

Staff members at SAIC are developing drafts of implementing procedures for theCMP, Milestone R048, for issue once the approval of the CMP has been obtained.Based upon an assumed approval of the CMP by August 30, 1986, this milestoneshould be complete on or about October 31, 1986.

Based upon SAIC discussions with WMPO quality assurance, the TMSS procedure,Issuance and Maintenance of Controlled Documents, -will be deleted. A draftNNWSI Project administrative procedure (AP 1.5) for both NNWSI Project andT&MSS controlled documents was submitted to quality assurance for review.

Several actions were approved including additions to the baseline to recorddelivery of two final environmental assessments.

The organization of the Baseline Policy, Program, and Project Guidance documentwas approved by WMPO during July and will be prepared for distribution as timepermits.

WBS 1.2.1.3 TECHNICAL DATA BASE MANAGEMENT

WBS 1.2.1.3.1 Tuff Data Base

At SNL draft versions of modified work plans and quality assurance levelassignment sheets for the tuff data base were completed. They were forwardedto WMPO for review and approval in July 1986.

SNL staff members continue work on the second draft of a proposed standardoperating procedure for the authorization and release of test data for inputinto the technical data base. The draft will describe the origination and flowof site, design, performance-assessment, and engineering material properties

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data into the tuff data base and the reference information base. This work hasbeen delayed by the preparation of modified work plans and quality assurancelevel assignment sheets.

Tuff data base staff members at SNL are preparing quality assurance proceduresfor software and for quality assurance auditing methods and requirements. Theyalso attended a training session on quality assurance auditing presented byWMPO on July 23-24, 1986, in Las Vegas, Nevada.

WBS 1.2.1.3.2 Computer Graphics

SNL personnel modified work plans and quality assurance level assignmentsheets, which were completed and forwarded to WMPO for approval during July1986.

WBS 1.2.1.3.3 Reference Information Base

Draft versions of modified work plans and quality assurance level assignmentsheets were completed at SNL and will be forwarded to WMPO for review andapproval by the end of July 1986.

WBS 1.2.1.4 TOTAL SYSTEMS PERFORMANCE ASSESSMENT

WBS 1.2.1.4.1 Flow and Radionuclide Transport

The SNL report entitled Preliminary Estimates of Groundwater Travel Time andRadionuclide Transport at Yucca Mountain Repository Site" (SAND85-2701) wassubmitted for printing. This report, which will satisfy Milestone R082,presents the assumptions, methods, and data used in a probabilistic approach tothe calculation of ground-water travel times and total radionuclide releasedinto the water table below Yucca Mountain.

A contractor report from Lawrence Berkeley Laboratory entitled HydrologicMechanisms Governing Partially Saturated Fluid Flow in Fractured Welded Unitsand Porous Nonwelded Units at Yucca Mountain" (SAND85-7114) was sent to WMP0for policy review (SNL Milestone N117). This report uses a discrete-fractureporous-matrix model and a composite-medium model to study the hydrologicalresponses to cycles of pulse infiltration.

WBS 1.2.1.4.2 Radionuclide Source Term

At SNL the NNWSI Project position paper describing the boundary of thedisturbed zone (Milestone M107) was revised based on previous review commentsand resubmitted for review.

Modified work plans and quality assurance level assignment sheets for this taskwere completed at SNL and submitted to WMPO for review.

WBS 1.2.1.4.4 Radionuclide Releases from Total System

During July 1986, SNL staff members assigned to this task-participated inwriting and review of Chapters 6 and 8 of the SCP. All other activities underthis task were suspended for the month.

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PLANNED WORK

At SNL the system requirements (SR) will be revised to incorporate WMPO reviewcomments. The revisions will include the addition of a matrix correlating eachsystem requirement with associated sections of the subsystem design requirementdocument. Similar matrices will be added to each section of the SR.

The first draft of the system description document (SD) will be completed inSeptember 1986 for review by SNL staff and management.

Documentation of NNWSI Project system studies in the NNWSI Project SystemStudies Register (SNL Milestone P126) will start when the NNWSI Project SEMPhas been completed and implemented.

A revised cost estimate of the Yucca Mountain repository surface facilities anda completely new cost estimate of the subsurface facilities will be completedat SNL per the final draft guidelines for repository cost estimates. Thistask was expected to be completed by August 1, 1986, but because of somecontingent software delays will probably be complete around August 15, 1986.

SNL staff members will resume rewriting the RCD/SC cost estimate report,including major text changes to the cost account codes and staffing to includethe DOE cost guideline direction.

The draft SEMP should be available for Technical Project Officer review inmid-August 1986.

Work on the SNL tuff data base task that is not exempt from the stop-work orderis suspended until the WMPO stop-work order is rescinded. When work resumes,the staff will continue on a search of NNWSI Project bibliography to identifyand organize all published data collected by the Project participants to date.Work will also begin on development of a new structure for the tuff data baseusing a relational data management system.

Work on the SNL reference information base task that is not exempt from thestop-work order is suspended until the WMPO stop-work order is rescinded. Whenwork resumes, the data base staff will continue to identify data for inclusionin the reference information base. The outline and format for the referenceinformation base will be finalized following Project review and comment. Aneffort will be initiated to apply modern, computerized data managementtechniques to storage of reference information base information.

SCP work during August and September 1986 at SNL will focus on reviews andrevision of Issue 1.6 on pre-waste-emplacement ground-water travel time.

PROBLEM AREAS

At SNL Revision of the SR and completion of the SD document will be delayed bywork on the SEMP.

The NNWSI Project stop-work order has delayed all work under the computergraphics task, except for work related to quality assurance and the SCP. SNL

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milestones R078 (the revised three-dimensional reference model of therepository site) and R079 (a technique for subterranean surface modeling forthe NNWSI Project repository: software documentation) will be delayed.

MILESTONE PROGRESS

The due date for SNL Milestone R073, the overall strategy for certification ofperformance-assessment models, was changed to September 1987 by the ChangeControl Board (CCB).

SNL Milestone M261, the Yucca Mountain site-specific mined geologic disposalsystem description, will be delayed since the first draft will not be completeduntil September 1986.

The SNL Milestone R058, the cost estimate of the Yucca Mountain repositorybased on design information developed for the RCD/SC, will be delayed becauseof work required by the SCP and RCD/SC. The estimated date of completion isDecember 24, 1986.

The estimated completion date for the SEMP (SNL Milestone M108) is October 15,1986.

The systems engineering review of the NNWSI Project (SNL Milestone R074)continues to be delayed and the estimated completion date is October 31, 1986.

A CCB change request will be submitted requesting cancellation of the SNLMilestone R075, preliminary geometrical and statistical synthesis of data fromYucca Mountain.

The SNL report on the NNWSI Project data priority study (Milestone M126) isdelayed; estimated date of completion is September 30, 1986. Additional SNLmilestones that will be delayed include: the summary report of data baseinteractions among NNWSI Project participants (Milestone R076); the descriptionof the organizational structural for the tuff data base (Milestone R089); thestatus report of NNWSI Project data base capabilities (Milestone R080); and thereport on the effect of heat and excavation on water flow in the vicinity ofthe waste package (Milestone Mill).

CCB action is in progress to change the due date of Documentation of theTOSPAC Volume 2: User's Manual and Sample" (SNL Milestone M128) to July 31,1987.

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COSTNNWS I

NNWSI PROJECTCOST PERFORMANCE GRAPH FOR JUL 1985

WBS: 1.2.1

A. BUDGETED COST OF WORK SCHEDULED (BCWS)B. BUDGETED COST OF WORK PERFORMED (BCWP)C. ACTUAL COST OF WORK PERFORMED ACWP)D. BUDGET AT COMPLETION (BAC)E. LATEST REVISED ESTIMATE (LRE)

Current

VARIANCES (Year To Date)F. SCHEDULE ARIANCE (B-A)G. COST URIANCE (B-C)H. AT COMPLETION UARIANCE (D-E)

Remarks: Cost variance s due to resources in Systems being diverted to the prepara-tion of the SCP and work on the Quality Assurance Level Assignment Sheets (QALAS).

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COST PERFORMANCE REPORTWBS LEVEL 4

U.S. DEPARTMENT OF ENERGYNNWSI PROJECT

For: JUL 1986 Date: August 21. 1986

1211121212131214

121

1.2.2 WASTE PACKAGE

OBJECTIVE

The primary objective of this task is to develop a technical basis andengineering capability to design, test, and fabricate a waste package that iscompatible with the hydrological conditions and geochemical environment in theunsaturated zone beneath Yucca Mountain.

ACTIVITIES

WBS 1.2.2.1 MANAGEMENT AND INTEGRATION

As part of the metal barrier function of the waste package, alternative metalsare under consideration. Project participants completed a tour and workingsession with Timet Corporation, Henderson, Nevada, on July 18. Timet committedto respond to a series of applicable subjects. Timet is the largest free worldtitanium producer.

WBS 1.2.2.2 PACKAGE ENVIRONMENT

Staff members at LLNL are addressing the implications and requirements of-thestop-work order and expending effort on the SCP.

WBS 1.2.2.3 WASTE FORM AND MATERIALS TESTING

WBS 1.2.2.3.1 Waste Form Testing

At LLNL, in the area of glass waste form testing, work continues on activitiesexempted from the stop-work order, including unsaturated testing at ArgonneNational Laboratory, writing and review of technical procedures, andpreparation of the SCP (which has preempted all work on the scientificinvestigation planning documentation for glass waste form testing). Staffmembers are also addressing the implications and requirements of the stop-workorder.

WBS 1.2.2.3.2 Metal Barrier Testing

LLNL personnel concentrated on the copper report and the SCP and addressed theimplications and requirements of the stop-work order.

WBS 1.2.2.3.3 Other Materials

Staff members at LLNL are addressing the implications and requirements of thestop-work order and concentrating on the SCP.

WBS 1.2.2.3.4 Integrated Testing

The efforts given at LLNL to the SCP and addressing the implications andrequirements of the stop-work order excluded any other activities for July.

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WBS 1.2.2.4 DESIGN, FABRICATE, AND PROTOTYPE TESTING

Activities exempt from the stop-work order at LLNL are preparation of theadvanced conceptual design (ACD) subsystem requirements document and review ofproposals for container closure and fabrication development contracts. Interimchange 38 to the WMPO Quality Assurance Program Plan is being reviewed inconjunction with resubmission of subtask quality assurance level assignmentsheets to WMPO. Staff members are also addressing the implications andrequirements of the stop-work order.

WBS 1.2 .2.5 PERFORMANCE ASSESSMENT

At LLNL the performance assessment section of SCP Chapter 7 has been internallyreviewed and revised. This section is in final typing. Staff members areaddressing the implications and requirements of the stop-work order.

Other activities at LLNL included assigning a QA level for the performanceassessment task and writing and internally reviewing scientific investigationplanning documentation. Early August issue to WMPO is expected.

MILESTONE PROGRESS

The LLNL NNWSI Project waste package system, a model description report(Milestone 276), is complete and will be submitted for final internal reviewprior to publication.

Progress on LLNL milestones C304, C319, and M343 has been delayed because ofthe redirection of effort required by the stop-work order.

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NNWSI PROJECT

COST PERFORMANCE GRAPH FOR JUL 1986WBS:1.2.2

COSTWBS: 1.2.2

JUL 1 986

E. LATEST REVISED ESTIMATE (LRE)

G. COST VARIANCE (B-C)

Current

Remarks: Cost and schedule variances are under the lO% threshold. No analysisrequired.

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For: JUL 1988 DATE: August 21, 1986

1.2.3 SITE INVESTIGATIONS

OBJECTIVE

The objective of this task is to determine whether Yucca Mountain is a suitablelocation for a high-level waste repository. The effort is divided into twoareas of study. The first is understanding the characteristics of the rockmass that lies below the surface of Yucca Mountain. This encompasses thegeology (structure and stratigraphy), hydrology (both saturated and unsaturatedzone), geochemistry (chemical reactions that can be expected when waste isemplaced), and mineralogy and petrology (the study of the materials that willcontrol the isolation and engineering characteristics of the rock). The secondis understanding the processes and events that could occur in the areasurrounding Yucca Mountain that could serve as potential disruptive forces.These efforts include the study of tectonics, seismicity, and volcanism, andthe regional hydrologic, paleohydrologic, and paleoclimatologic systems.

ACTIVITIES


The stop-work order issued to the United States Geological Survey (USGS) inMarch 1986 remained in effect through July and almost all site characterizationtechnical activities continued to be suspended throughout the month. A draftof the USGS responses to the quality assurance findings is nearly complete andwill be transmitted to WMPO next month. Prototype scientific investigationplanning documentation and corresponding quality assurance level assignmentsheets (ALAS) were submitted to WMPO for review and approval. Upon approval,the ALAS will be prepared to the same level of detail and content.

The Site Integration Group (SIC) assisted the WMPO Regulatory and SiteEvaluation Branch in a review of quality assurance level assignments andassociated site investigation planning documentation for the site and relatedWBS elements.

Most of the SIC staff at SAIC has been assigned to a Permanent Internal ReviewCommittee (PIRC) to review chapters of the SCP. This commitment is expected tocontinue at least until the SCP is collated into a single document.

The Core Library Task Force completed a review of a portion of the core fromdrill hole G-4 and prepared a draft report to the Core Library SteeringCommittee. The steering committee presented its recommendations to WMPO and ispreparing a document for WMPO. Work on the development of the new core storagefacility (CSF) continued under direction of SAIC and WMPO personnel. SAICstaff members began work on the computer tracking software, the consolidatedand overpacked spent fuel (CSF) functional requirements, the sample handlingprocedures, definition of equipment needs, and staffing requirements. Staffmembers involved with the exploratory shaft facility (ESF) visited the TBEGcore facility in Austin, Texas, to examine their procedures for handling SALTRepository Project Office salt core from West Texas. Two staff members of theSAIC Site Management and Integration Branch have been assigned temporarily tothe task of developing the concepts for sample management, including the CSF.

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The SIG is assisting in the preparation of materials for a briefing on sitecharacterization to the State of Nevada. The briefing is tentatively scheduledfor August 27 or 28, 1986, in Carson City. The SIG is also preparing theletter report for the State on the period of site characterization betweenMay 28, 1986, and release of the SCP. The report is in review and is scheduledfor completion about mid-August 1986.

WBS 1.2.3.2 GEOLOGY

WBS 1.2.3.2.1 Geologic Investigations

Modified work plans and quality assurance level assignment sheets for this taskwere redrafted at SNL and forwarded to WMPO. A draft study plan has beencompleted and will be followed by test procedures and individual technicalprocedures for detailed work. When these actions are completed and approved, acontract for mapping and trenching can be negotiated.

A structural contour map, constructed by USGS personnel, of the base of theTopopah Spring tuff will be incorporated into a report on the variations ofthat member of the Paintbrush Tuff on Yucca Mountain. The scientificinvestigation planning documentation on Characterization of the Vertical andLateral Distribution of Stratigraphic Units for Site Geology Investigations".was forwarded to WMPO for approval.

A USGS paper entitled Geologic Framework of Yucca Mountain, Nevada," wil- bepresented at the September meeting of the American Chemical Society in Anaheim,California, as part of a symposium organized on geochemical processes at YuccaMountain.

WBS 1.2.3.2.2 Geophysical Investigations

WBS 1.2.3.2.2.1 Gravity and Magnetics

At USGS additional modeling of the new ground-magnetic data near Lathrop Wellscontinues to support the hypothesis of a reversely polarized cinder cone buriedat a depth of 600 to 1,000 feet. A study of well data south of Lathrop Wellslocated a well that was drilled through basaltic rocks deposited by anephermeral stream." Thus, the Lathrop Wells anomaly may be the source of thedetrital basalts. A further study of the mag properties of exposed intrusiveand volcanic rocks in the Crater Flat-Yucca Mountain area is needed.

WBS 1.2.3.2.2.3 Rock Properties

At USGS the field strength of the newly operational Alpha Scientificelectromagnet has been established and imprinting of isothermal remnantmagnetics on small core samples has begun.

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WBS 1.2.3.2.3 Site Stability

WBS 1.2.3.2.3.1 Tectonics and Volcanism

Personnel at USGS discussed needed fault studies at Yucca Mountain and decidedto review trench studies at a proposed September field trip. The group wouldexamine previously mapped trenches to determine if remapping of any oldtrenches is needed before attempting new field studies.

USGS and Los Alamos representatives met on July 3 to discuss discrepancies inthe dating of the basalt from the Lathrop Wells cone. The currently acceptedage is 270,000 years but current age estimates range from a negative age(-80,000 years) to a high of 500,000 years. The geomorphic developmentsuggests an age of about 100,000 years. The problem will be resolved usinghigh precision K-Ar dating, cation-ratio rock varnish dating, and U-seriesdating. Resolution of the discrepancies is vital because the true age affectsthe probability of volcanism, the age of the Q alluvial deposits, and thus theage of faulting at Yucca Mountain.

The scientific investigation planning document for volcanism was revised by LosAlamos staff members after technical review and submitted to WMPO. Qualityassurance procedures are being developed for four separate items undervolcanism to replace the volcanism Quality Assurance Work Plan.

WBS 1.2.3.2.3.3 Seismicity and Strain

USGS personnel continued operation of the seismic network for recording naturalseismic events in southern Nevada during July.

WBS 1.2.3.3 HYDROLOGY

Personnel at the Materials Test Lab continued calculations on tests completedprior to the stop-work notification. They are using ultracentrifuge equipmentto test dummy samples. They are also organizing all NNWSI Project reports,dating back to 1983, and sorting test reports, data sheets, and calculations bydrill hole and by year.

WBS 1.2.3.3.1 Stream Flow

Heavy rain occurred at the Nevada Test Site (NTS) on the evening of July 23.The Desert Rock Weather Station reportedly received 1.27 inches of rain between5:30 and 10:00 p.m. Local flooding of roadways was reported in Mercury. AllUSGS rain gauges and drainages of concern at NTS were visited on July 25. Flowwas reported only in the Amargosa River tributary near Mercury (Mercury Wash atHighway 95 crossing near Point of Rocks). The estimated peak flow there was atabout 60 cfs and data were collected to compute the peak flow. Moderaterainfall was general in the Yucca Mountain area but no runnoff was noted.

WBS 1.2.3.3.2 Ground-water Flow Analysis

Lawrence Berkeley Laboratory personnel have completed the design andformulation of a computer code for modeling solute transport to discretefracture networks. Program debugging and testing remains to be done. Discrete

3-3

fracture networks are generated on the basis of statistics describingprobability density functions for fracture aperture, length, orientation, anddensity. The model is two dimensional and capable of simulating eithersteady-state or transient flow.

At USGS a review of interpretive techniques that could be useful in analyzingtracer-test results within the framework of an equivalent porous mediumincluded both analytical and numerical methods. No porous-media model isadequate for use in evaluating all flow and transport hypotheses beingconsidered by the Project. While using many analytical methods in the courseof data interpretation is a workable alternative, the time required to becomefamiliar with a number of numerical codes, as well as the time required to testeach numerical code under the unique fracture-rock conditions at Yucca Mountainwould be prohibitive. No decision has been made to modify existing numericalcodes to meet Project needs or to develop a new code.

USGS personnel completed the data-collection phase of an analysis of earth-tideand barometric effects on water levels. Pressure transducers were removed fromthe c-holes during the week of July 21. Results of the study will be used inan attempt to estimate aquifer porosity.

WBS 1.2.3.3.3 Saturated-Zone Hydrology

USGS personnel continued water-level monitoring at Yucca Mountain. Thisactivity is exempt from the stop-work order. Hole UE-25 WT#6 (located north ofDrill Hole Wash), which previously was measured biweekly, was instrumented forcontinuous monitoring.

USGS personnel met with WMPO representatives on July 1 to discuss anappropriate strategy to evaluate the potential impact of ground-waterwithdrawal near Yucca Mountain on water-table altitude. A two-dimensionalmodel will be used to simulate the effect of pumping in western Jackass Flatson the NTS. This and other simulations pertaining to potential consumptive useof ground water in the subregional model area will be assembled in a report.

WBS 1.2.3.3.4 Unsaturated-Zone Hydrology

The preliminary drafts of the Prototype Investigation Plans (PIPs) werecompleted at USGS for all projects and submitted to Los Alamos for review.Los Alamos and DOE representatives reviewed all PIPs presentations andsuggested a down scaling of activities.

WBS 1.2.3.4 GEOCHEMISTRY

WBS 1.2.3.4.1.1 Ground-water Chemistry

Los Alamos personnel completed the scientific investigation planning documenta-tion for ground-water chemistry. The plan is undergoing technical reviewbefore submittal to WMPO.

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WBS 1.2.3.4.1.2 Natural Isotope Chemistry

The scientific investigation planning documentation and quality assurance levelassignments for this task were prepared at Los Alamos and submitted for reviewas part of the work required to lift the stop-work order.

WBS 1.2.3.4.1.3 Hydrothermal Geochemistry

Los Alamos personneL prepared the scientific investigation planning documenta-tion for this task and review is near completion. These documents emphasizethe need to understand the role of aqueous silica activity in controllingmineral stability in Yucca Mountain and the need for kinetic data on theevolution of silica polymorphs; an understanding is also needed of therelationship between that evolution and evolution of aqueous silica activity.Revision of the SCP also continued.

WBS 1.2.3.4.1.4 Solubility Determination

Solubility measurements being performed for Los Alamos at Lawrence BerkeleyLaboratory are continuing on americium, plutonium, and neptunium in Well J-13water at pH 6, 7, and 8.5 and at 60 C. This work is exempt from the stop-workorder.

Los Alamos staff members reviewed and commented on four Nuclear RegulatoryCommission Generic Technical Positions.

WBS 1.2.3.4.1.5 Sorption and Precipitation

Los Alamos staff members completed parallel concentration dependent sorptionmeasurements (isotherms) with neptunium both in and out of the carbon-dioxide-controlled atmosphere box, and samples are being counted. They also organizedand formatted data from the studies of the effect of ground-water chemistry onthe sorption behavior of elements for Milestone M316.

Additional experiments have been performed by Los Alamos personnel to determinethe migration of Pseudomonas bacteria through Calico Hills Tuff. Resultssubstantiate earlier studies and conclusively indicate that bacteria are mobilein Calico Hills tuff. Microbes studies have been exempted from the stop-workorder.

WBS 1.2.3.4.1.6 Dynamic Transport Process

All Los Alamos work on crushed tuff and fractured tuff columns has stopped inaccordance with the stop-work order.

Section 8.3.5.8.1 of the Site Characterization Plan was reviewed at Los Alamosand comments and responses were forwarded to the Permanent Internal ReviewCommittee 4 (PIRC 4). Sections 8.3.5.4 and 8.3.5.8 of the SCP were reviewed byLos Alamos personnel for the August PIRC 4 meeting.

WBS 1.2.3.4.1.7 Retardation Sensitivity Analysis

The scientific investigation planning documentation for the Los Alamosretardation sensitivity analysis task was completed and the quality assurancelevel assignment sheets were completed.

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WBS 1.2.3.4.2 Mineralogy and Petrology

In July, Los Alamos research was stopped until the 16th, when it was learnedthat the stop-work order issued on June 10 had been lifted for mineralogy andpetrology studies. The first part of July was spent in preparing scientificinvestigation planning documentation and quality level assignments formineralogy and petrology studies in order to remove the stop-work order. Atthe same time, work was performed on the preparation of analytical proceduresfor point counting, electron microprobe analysis, x-ray fluorescence analysis,and acceptance of mineral standards for electron microprobe analysis. Aprocedure was also prepared for overall sample identification and control inorder to provide sample traceability through all of the preparation andanalysis procedures performed at Los Alamos for mineralogy and petrologystudies.

In the latter half of July, Los Alamos Milestone M331, lateral continuity andprobabilistic models in sorptive mineral zones underlying Yucca Mountain,Nevada, was completed. This milestone is a statistical analysis of thequantitative x-ray diffraction data that have been collected from drill coresand drill holes during mineralogy and petrology studies.

WBS 1.2.3.5 DRILLING

WBS 1.2.3.5.1 Core Library

Representatives from Los Alamos, SAIC, SNL, DOE, and USGS met in Mercury onJuly 10 and 11 to discuss the traceability of core samples, particularlyconcerning depth of origin. Documentation of sample traceability is incompletefor the drill core samples analyzed to date, and all data based on thesesamples may have to be reassessed if the results of analyses are to be used forlicensing. Work has begun on assessing the impact of this conclusion onmineralogy and petrology studies at Los Alamos and on other studies(e.g., transport modeling) that will incorporate the results of mineralogy andpetrology studies. Solutions may be sought through peer review or by testingcurrent mineralogic and petrologic interpretations against core from futuredrill holes.

WBS 1.2.3.5.2 Drilling, Construction, Engineering

Fenix Scisson (F&S) staff members developed three QA procedures for reviewand approval. They are entitled Development of Drilling and Additional WorkPrograms, Drilling Specialist Surveillance Procedure, and Review/Approval forRevisions/Changes in Drilling and Additional Work Programs.

Test hole UZ-8 remained at a temporary depth of 58 feet as all drillingcontinued to be suspended under the stop-work order.

H&N and SAIC personnel worked on the scientific investigation planningdocumentation for the NNWSI Project Atlas of Field Activities (Atlas) and ondeveloping forms for information gathering and procedures for the Atlas.

H&N submitted a budget estimate, with supporting detail to WMPO.

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.

Map reference data from Nevada State coordinates were converted at HN tolongitude and latitude and a map of these coordinates for the J-13 water welllocations was prepared and delivered to WMPO.

H&N survey personnel updated mapping in Area 25 at the NTS and laid out mappingtargets in test pits at Fran Ridge as requested by USGS.

WBS 1.2.3.5.3 Field Geology and Hydrology

F&S personnel structured the computer data base for fracture data entry,developed a methodology to obtain moisture retention curves from core samples,and assisted the USGS with instrument design and calibration for matrixpotential measurements on core at Test Cell C," with maintenance ofprecipitation stations, and with prototype testing of fracture mappingprocedures for the exploratory shaft and drifts.

WBS 1.2.3.6 ENVIRONMENT

WBS 1.2.3.6.1 Environmental Surveys

Work continued at SAIC on the Radiological Monitoring Plan (RMP) and thePre-Site Characterization Radiological Monitoring Plan (PSCRMP). The scope ofthe plan covers monitoring activities before significant site characterizationactivities begin. The purpose of the monitoring program is to measurebackground radon and resuspended particulate radioactivity so that incrementalreleases caused by site characterization can be quantified. A draft of thePCCRMP was forwarded to WMPO for review. A pathways analysis is also inprogress to support development of the plan.

WBS 1.2.3.6.2 Transportation

Approval to award a contract to Deleuw Cather Company has been received. Thecompany will prepare a plan to develop data needed to assess the feasibility ofalternate rail access routes to Yucca Mountain.

The route used for recent shipments of spent fuel from the E-MAD facility toIdaho National Engineering Laboratory (U.S. Highways 95, 6, and 50) is beingadded to the draft Nevada Routing Study.

At SAIC, staff members completed a draft final report on the frequency ofinteractions between Air Force activities and repository operations. At therequest of TMSS management, a peer review by corporate SAIC management wasinitiated. The review will take place during the week of August 11 in LasVegas. The review will cause a delay in the transmittal of the report to WMPO.

SAIC Transportation Branch personnel prepared a draft paper on transportationissues based on recent public events. The paper will support the approach tocoordinate future analytical work with other NNWSI Project components. Thepaper is currently in internal review.

Revisions in response to an internal review were completed at SAIC on thedocumentation of Nevada population information. This information was used inthe Environmental Assessment to estimate regional impacts of nuclear wastetransportation.

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WBS 1.2.3.7 SCIOECONOMICS

Work continued at SAIC on the Socioeconomic Monitoring and Mitigation Plan(SMMP). Staff members defined issues and parameters to be monitored anddeveloped plans to monitor the parameters.

At SAIC the tourism report ("High-Level Nuclear Waste Transport and StorageAssessment of Potential Impacts on Tourism in the Las Vegas Area"), completedin May 1986, was published and distributed.

WBS 1.2.3.8 PERFORMANCE ASSESSMENT - GEOCHEMICAL MODELING CODE E3/6

At LLNL review of the draft scientific investigation planning documentation forthe EQ3/6 subtask is in progress and should be completed next month.

The quality assurance level assignments for the entire Geochemical ModelingCode EQ3/6 subtask have been completed by LLNL staff members and will besubmitted to WMPO for approval as soon as internal approvals are complete. Thesoftware A requirements and procedures review was completed and the suggestedchanges are being evaluated. The coding standards and code developmentsections of the E3/6 AP are being revised and should be complete next month.

Work by LLNL for the Office of Nuclear Waste Isolation revealed and corrected anumber of bugs in E3NR, E6, and EQLIB. The codes now run some waste formdissolution calculations that led to the detection of these problems. Furtherimprovement needs have been indicated but not yet carried out, and efficiencyis less than it should be.

PLANNED WORK

When the stop-work order is lifted, Los Alamos field and laboratory workinvolved with determining infiltration into Yucca Mountain will commence, theuranium-series disequilibrium feasibility study will be completed, sorption andprecipitation work will resume on milestones that were originally due inSeptember, and apparatus for the dynamic transport process task will be checkedand repaired as needed.

Los Alamos staff members will review and revise their contribution to Section8.3 of the SCP.

Los Alamos staff members will implement kriged estimates for small data sets asa routine alternative by Sandia National Laboratories (SNL), reconsider aprobabilistic version of the MKM interpolation method that SNL is currentlyusing, and consider the problem of constructing a probabilistic fault model(milestones to be proposed).

At Los Alamos data from the Topopah Spring Member of the Paintbrush Tuff willbe compared with modal count data of the matrix and the distribution of glass(milestones to be proposed).

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In August, Los Alamos mineralogy and petrology studies will focus on thecompletion of analytical and sample tracking procedures. Milestones R345,R319, and R323 will be pursued.

PROBLEM AREAS

Progress on LLNL technical milestones for the EQ3/6 subtask has been delayeddue to the redirection of effort required for the completion of required QAdocuments.

A nonconformance report was issued by DOE/NTSO because of the HN response tothe request by USGS, Denver, for mapping support at the Fran Ridge test pits.No NNWSI Project work will be initiated by HN unless officially authorized bythe HN NNWSI Project TPO office. The TPO office will ensure that criteria andQA level assignments have been approved by WMPO/NTSO prior to authorizing anywork.

MILESTONE PROGRESS

Los Alamos Milestone M303 (ground-water chemistry at Yucca Mountain, Nevada,and vicinity) was completed and sent to WMPO for review on July 30.

Los Alamos Milestone R320, Petrographic Variation of the Topopah Spring Tuff,Matrix Within and Between Cored Drill Holes, Yucca Mountain, Nevada," wascompleted and sent to WMPO for review on June 27, 1986, and Milestone M331,"Lateral Continuity and Probabilistic Models in Sorptive Mineral UnderlyingYucca Mountain, Nevada," was sent to WMPO on July 30.

The preliminary validation of fault and tectonic environment for repositorysurface facilities (SNL Milestone N448) is delayed in line review.

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N

NNWSI PROJECTPERFORMANCE GRAPH FOR JUL 1986

WBS: 1. 2. 3

Remarks: The cost underrun and delayed schedule partially result from the stop-workorder issued in March 1986. Site drilling, core sampling, and almost all sitecharacterization technical activities are suspended.

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For: JUL 1986 DAte: August 21, 1986

1.2.4 REPOSITORY INVESTIGATIONS

OBJECTIVE

The objective of this task is to develop the engineering capability to design,construct, operate, and decommission a repository in tuff. Four specifictechnical areas are involved that include (1) determination of the physical andmechanical properties of the rock matrix and rock mass that are important tothe design and construction of an underground structure; (2) engineeringanalysis and evaluation of technical details that are important to the designand operation of a repository; (3) development of the techniques of sealing arepository as part of decommissioning; and (4) preparation of a site-specificdesign that will be accommodated within the development of the equipment toconstruct the repository, handle the waste and waste package, and transfer thewaste package within the repository system.

ACTIVITIES


Hanford Engineering Development Laboratory submitted a draft of the report onthe cask-receiving operation. The report is currently in review. Completionof this review by SNL satisfies Milestone M803.

Other SNL activities for this task were suspended during July because of theeffort required for SCP Section 6.4.

WBS 1.2.4.1.2 Basis for Design

The modified work plan and quality assurance level assignment sheets for thisSNL task were approved by WMPO.

The first change to the subsystem design requirement document was made. Thischange (Engineering Change Request 001, Revise Criteria for Air ConditioningDesign Conditions) introduced the use of the change-control procedure describedin QAP III-6. This change-control process will be very important incontrolling baseline design information.

The development of a methodology with a technical basis for a parameter studyof ground motion and surface rupture hazard evaluation for the NNWSI Projectwas completed at SNL and a draft report was prepared for peer review. The USGShas been requested to perform a peer review of the draft report. A designreview meeting on this task was held on June 27, 1986.

Approximately 17 interface control drawings will be produced to establish andcontrol design boundaries and interfacing design features between NNWSI Projectdesign organizations. They will depict the physical and functional details ofinterfaces that require coordination to establish and maintain compatibilitybetween cofunctioning equipment, items, or facilities.

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WBS 1.2.4.1.3 Major Design Deliverables

At SNL the preparation of Chapters 6 and 8 of the SCP and quality assurancelevel assignment sheets superseded all activities under the major designdeliverables task for the month of July 1986.

WBS 1.2.4.1.4 Engineering Design Support: Special Studies

At SNL modified work plans, quality assurance level assignment sheets, andquality assurance plans were written for design support.

WBS 1.2.4.1.5 Management and Integration Support

SAIC staff members submitted comments to WMPO on the draft Phase II proposalfor the Prototypical Rod Consolidation Demonstration Project.

WBS 1.2.4.2 DEVELOPMENT AND TESTING

WBS 1.2.4.2.1 Rock Mechanics

WBS 1.2.4.2.1.1 Rock Mass Analysis

Personnel at SNL continued to work on the modified work plans, the qualityassurance level assignment sheets, and sections of the SCP. Work on SCPChapters 6 and 8 superseded all other work under this task. Tasks describedbelow are in support of the SCP.

Revision of the draft of "Analysis for -Tunnel Field Experiment Small-DiameterHeater" (SAND85-7115) received from RE/SPEC, Inc., continues slowly. This workhas been delayed because of other commitments.

The effort at SNL planned to summarize the results pertinent to ThermomechanicsAnalysis 7 was delayed because of other commitments. The results will bereviewed with the intention of combining all of the work into a report as asupporting reference to the RCD/SC.

WBS 1.2.4.2.1.2 Field Testing

G-Tunnel was closed from June 30 to July 11, 1986, for the annual vacation. Thestop-work order for the welded tuff mining evaluations was lifted on July 15,1986, and work resumed on permeability testing supporting those evaluations.

WBS 1.2.4.2.1.3 Laboratory Properties

A draft version of a quality assurance procedure on sample identification andhandling was completed and submitted for internal SNL review.

WBS 1.2.4.2.1.4 Water-Migration Analysis

SNL personnel made quality assurance level assignment sheets for ten activitiesunder this task and sent them to WMPO. As supporting documents, a modifiedwork plan and quality-assurance criteria assignment forms were also sent.

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quality-assurance procedures for instrument calibration and indication of thestatus of items are in review at SNL and portions of the Quality AssuranceProgram Plan are being revised.

The document entitled "Calculation of Hydrologic Properties for Tuffs fromYucca Mountain, Nevada, Using Mercury Porosimetry Results" received peer-reviewapproval and was submitted to line review at SNL. The report supports SNLMilestone N498.

The SNL report entitled Influence of Transverse Microfractures on theImbibition of Water into Initially Dry Tuffaceous Rock" (SAND86-0420C), whichdocuments results of an imbibition experiment, has been submitted to peerreview. The paper has been accepted for presentation at the next AmericanGeophysical Union meeting.

WBS 1.2.4.2.2 Equipment and Instrumentation Development

The modified work plan to support quality assurance level assignment sheets wasrevised at SNL in late June and again in mid-July 1986 to reflect changesmandated by WMPO. The revised plan and the assigned quality-assurance levelswere approved by WMPO on July 23, 1986. With this approval, the stop-workorder on the equipment engineering task was lifted.

Representatives from SNL, the Robbins Co., and Eby Mine Services attended adesign review meeting on the development prototype boring machine on July 1,1986. A report documents the findings and recommendations of the reviewcommittee. In general, the committee found the boring machine design to becomplete and workable. Several relatively minor errors in the design anddesign drawings were discovered, and these will be corrected during thefabrication phase of the boring machine.

WBS 1.2.4.2.3 Sealing

WBS 1.2.4.2.3.1 Seal Performance Requirements

During July 1986, work at SNL on Chapters 6 and 8 of the SCP and the modifiedwork plan to support quality assurance level assignments superseded most of theactivities under this task. Preparation of the report entitled DesignRequirements and Materials Recommendation for the NNWSI Project RepositorySealing Program" (Milestone P404) resumed.

WBS 1.2.4.2.3.2 Sealing Materials Evaluation

Staff members at Los Alamos continued work on supporting documents for the SiteCharacterization Plan. Pennsylvania State University completed revision of thereport Preliminary Survey of the Stability of Silica-Rich Cementitious Mortars(82-22 and 84-12) with Tuff." Computer readable versions of reports on theancient concrete, CON-14, and 82-22 have been received from Pennsylvania StateUniversity.

WBS 1.2.4.2.3.3 Seal Concepts Development

At SNL work on Chapter 6 of the SCP and on the modified work plan to supportquality assurance level assignment sheets superseded all other activities.

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WBS 1.2.4.3 FACILITIES

WBS 1.2.4.3.2 Surface Facilities

SNL placed a contract to perform special studies and develop a referenceconfiguration for the advanced conceptual design with Bechtel National, Inc.However, because of the WMPO stop-work order, the current scope of work isconfined to those tasks that support the SCP, RCD/SC, seismic position paper,management, and planning. These tasks include the development of an operationsplan, consolidation study, repository options study, preclosure safety studies,development of interface control drawings, supporting the development ofissues-resolution strategy, design margins philosophy study, and development ofa -list.

A draft report on the preclosure safety analysis study is currently under SNLinternal technical review.

WBS 1.2.4.3.3 Shaft/Ramps

At SNL quality assurance level assignment sheets have been made and approvedfor the activities under this task.

SNL personnel completed the outline for the special study on hoist, headframe,and collar design. This study will be done by Parsons Brinckerhoff uadeDouglas prior to the start of the advanced conceptual design. The study willintegrate hoist selection, headframe design, and the ventilation inletstructure for the man and materials shaft.

WBS 1.2.4.3.4 Underground Excavations

Personnel at SNL developed quality assurance level assignment sheets for theactivities under this task. The assignment sheets were approved and themodified work plan reflecting these new quality-assurance levels was completed.

Outlines for special studies to be done prior to the start of AdvancedConceptual Design have been completed, reviewed, and accepted by ParsonsBrinckerhoff Quade Douglas as follows:

Repository Options StudyEmplacement Orientation StudyConstruction Contingency PlanUnderground Facility BoundaryRepository Operations Plan

SNL staff members finalized the design layouts for the underground wastestorage area reflecting commingling of spent fuel and defense high-level waste.These layouts will be included in the RCD/SC. Analyses supporting thesedesigns are complete and will be included in the appendix of the RCD/SC.

The contract modification incorporating a modified scope of work for theParsons Brinckerhoff Quade Douglas (PBQ&D) contract has been approved. Thismodified contract was approved by PQ&D and is now in effect.

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SNL personnel are making plans to visit an old mine developed in welded tuff inthe Creed, Colorado, area. SNL researchers will investigate the applicabilityof the information that can be obtained from this mine based on similarity ofgeology, depth, and opening size. If the mine proves analogous to thepotential repository at Yucca mountain, a wealth of historical information canbe obtained on long-term stability of underground openings in tuff, since thismine has openings that are more than 70 years old.

WBS 1.2.4.3.5 Underground Service Systems

SNL personnel completed an outline for the ventilation system report requiredfrom Parsons Brinckerhoff Quade Douglas under the new scope of work. Thisreport will address the impact of radon and moisture on the ventilation system,as well as the normal design of the ventilation system required to support theAdvanced Conceptual Design.

Personnel at SNL completed the modified work plan for activities under thistask. The plan includes the new approved quality assurance level assignmentsheets.

Preliminary work at SNL does not substantiate the need for high efficiencyparticulate air filtration of the waste-emplacement exhaust. Further work willbe based on the accident analyses currently being performed by BechtelNational, Inc. There would be a great cost and operational benefit if thesefilters can be eliminated, a goal that warrants additional effort.

WBS 1.2.4.4 OPERATIONS AND MAINTENANCE

On July 9-10, 1986, SNL staff members met with personnel from ParsonsBrinckerhoff Quade Douglas and Bechtel National, Inc., to review progress onthe Reference Configuration Operating Plan. They identified approximately 12drawings or illustrations to be produced as a part of this task. Areliability-availability-maintainability methodology was presented. Thisanalysis will include the use of functional block diagrams and preliminaryfailure modes and effects analysis tables. By the end of July, a block flowdiagram of the waste-handling building operations was issued for review.

WBS 1.2.4.6 REPOSITORY PERFORMANCE ASSESSMENT

WBS 1.2.4.6.1 Performance Code Development and Certification

At SNL work to complete the modified work plans, the quality assurance levelassignment sheets, and sections of Chapters 6 and 8 of the SCP continued andsuperseded all other work under this task. As permitted by the WMPO stop-workorder, the following reported work consists of documentation of previous work.

SNL personnel continued work on verification and validation plans for thermaland mechanical codes to meet criteria in NNWSI Project SOP-03-02. Thecompletion of a draft of this plan depends on completion of commitments to SCPChapters 6 and 8 and preparation of the modified work plan and qualityassurance level assignment sheets.

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SNL staff members reviewed and returned the draft letter report onThermomechanics Analysis 12, JEM Verification Calculations--Phase I toRE/SPEC. A final letter report will be revised and submitted in August 1986.

The SNL Applied Mechanics Division staff is in the process of documenting thecoding of the compliant joint model in the code JAC. Currently the work isbeing directed toward documentation of the link between the compliant jointmaterial model and JAC . The work was described in a draft report entitled AComputational Model for Jointed Media with Orthogonal Sets of Joints"(SAND86-1122).

WBS 1.2.4.6.2 Design Analysis

At SNL SCP Section 6.4.2 describing the status of Issue 1.12 and subsumedinformation needs (design underground facility and engineered barriers incompliance with 10 CFR Part 60.133 and to support performance assessment) wascompleted in draft form and submitted for review.

SNL personnel also prepared, reviewed, and revised SCP Section 6.4.8.2.3,results for analyses on underground opening design and underground ventilationsystem design.

Quality level assignment sheets for the SNL design analysis task have beenapproved.

WBS 1.2.4.6.3 Preclosure Safety Analysis

The modified work plan and quality assurance level assignment sheets for theSNL preclosure safety analysis task were completed and submitted to WMPO.

PLANNED WORK

The peer review of a contractor report by Bechtel National, Inc., will resume.The document, which will satisfy SNL Milestone R060, is entitled AnEngineering Study of the Impact on Costs and Schedule of Using a MonitoredRetrievable Storage Facility in Conjunction with a Repository in Tuff at YuccaMountain" (SAND85-7112).

At SNL commitments to the quality assurance level assignment sheets, themodified work plan, and SCP chapters 6 and 8 will supersede all work plannedfor the rock mass analysis task. When work resumes

1. A problem-definition memo will be prepared to define an analysis ofthe -Tunnel mining evaluation experiment. The experiment wasanalyzed previously, but upon developing the drift, the stratigraphywas found to be different than had been envisioned. Also, the roomshape that was actually developed was dimensional in accord with thecurrent reference shape for the repository horizontal emplacementscheme.

2. A problem-definition memo will be prepared to define.an analysis ofthe -Tunnel pressurized slot experiment. An experiment of this type

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was analyzed previously in support of the planned exploratory shaftexperiment. This analysis will be specific to the geology andstructure at the experiment location in -Tunnel.

3. The report entitled "Analysis for C-Tunnel Field ExperimentSmall-Diameter Heater" (SNL Milestone R083) will be revised.

4. Work will continue on Thermomechanics Analysis 13, Analysis of RockMass Properties as Determined through a Compliant Joint Model."

5. Work will be initiated on Thermomechanics Analysis 14, "Analysis ofIn Situ Stress at Yucca Mountain using a Compliant Joint Model."

The following laboratory properties work is planned at SNL for August throughOctober 1986:

Two draft reports on properties of the Topopah Spring Member will becompleted. Report subjects include thermal properties of lithophysae-rich material and a summary of bulk, thermal, and mechanical properties ofmatrix material.

Contracts will be placed to perform heat-capacity measurements andhigh-temperature, low-strain-rate tests.

Mechanical testing will be initiated (assuming approval of qualityassurance level assignment sheets) to determine matrix tensile strengthand potential anisotropy of compressive strength and elastic properties ofthe welded, devitrified Topopah Spring Member.

Receipt of a quality assurance plan from The Robbins Co. for the contract workon the development prototype boring machine was expected at SNL in late July1986. Following approval of the plan, the contract to fabricate and test themachine will be placed.

During August 1986, work at SNL on the Reference Configuration Operating Planwill continue with the development of requirement allocation sheets andstaffing plans.

SNL staff members will participate in an Exploratory Shaft Test Plan workshopon thermal and mechanical field tests to be held on August 7-8, 1986. Theprimary objective of the workshop is to ensure that the thermal and mechanicaltests currently planned for the exploratory shaft adequately address thedesign, model validation, and performance assessment data needs as presentlydefined.

Work will continue at SNL on a verification and validation plan for thermal andmechanical codes in order to meet criteria in NNWSI Project SOP-03-02. First,a concentrated effort is being made to write a plan for documenting "compliantjoint material models."

During August 1986 at SNL, the design analysis sections (including appendices)for the RCD/SC will be reviewed and rewritten.

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PROBLEM AREAS

The recent stop-work order may affect the schedule of the advanced conceptualdesign, special studies, and the development of the reference configuration forthe advanced conceptual design if Bechtel is asked to stop the work. Thisstoppage may also affect the contract negotiated for the current effort.

Priority given to the quality assurance level assignment sheets, the modifiedwork plan, and SCP Chapters 6 and 8 superseded all work at SNL planned for therepository performance code development and certification task. All workschedules are expected to be delayed accordingly.

SNL design analysis milestones will be delayed because of priorities given toother Project work such as the SCP and RCD/SC.

The stop-work order will affect the due dates for the planned retardationsensitivity analysis milestones due in September and the following fiscal year.

MILESTONE PROGRESS

SNL Milestone N430, the start of the repository advanced conceptual design isdelayed.

CCB action is in progress to change the date for SNL Milestone R064, theadvanced conceptual design review meeting; the estimated completion date isJune 30, 1987.

Delayed SNL milestones included: N426, submission of the advanced conceptualdesign annotated outline to WMPO for review (the estimated completion date isJune 30, 1987); R015, the update repository design plan incorporatingpreclosure performance-assessment information (estimated completion date isJune 30, 1987); M437, the report on pressurized slot measurements (estimatedcompletion date of October 15, 1986); M455, the report on G-Tunnel undergroundfacility summary (estimated completion date of September 30, 1986); N403,recommended matrix properties of Topopah Spring Member (estimated completiondate is October 31, 1986); N429, parameter effects on mechanical properties ofthe Topopah Spring Member (estimated completion date is August 31, 1986); M432,report on rock mass constitutive model (estimated completion date is October30, 1986); and M414, report on far-field thermal mechanical effects (estimatedcompletion date is February 20, 1986).

SNL Milestones M295, N440, and N450 are delayed in management review.

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n


JUL 1986WBS:1.2.4

Remarks: The cost underrun and behind-schedule conditions are a result of thedelay in the start of the Repository Advanced Conceptual Design (ACD). The redirectionof resources to the SCP, and the stop-work order.

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For: JUL 1986 Date: August 21, 1986

12411242124312441245

1.2.5 REGULATORY AND INSTITUTIONAL INVESTIGATIONS

OBJECTIVE

The objective of the regulatory and institutional investigations task is toprovide the capability for interfacing with all the institutions and to meetthe requirements identified in various laws and regulations pertaining to thesiting, design, and construction of a nuclear waste repository and a test andevaluation facility. The principal laws and regulations which govern thelicensing of these include the Atomic Energy Act of 1954, the NationalEnvironmental Policy Act (NEPA) of 1969, and the Nuclear Waste Policy Act(NWPA) of 1982, 10 CFR Part 60, and 40 CFR part 191.

ACTIVITIES


At SAIC staff members completed the FY 87 budget critique based on the FY 88WPAS pass back figures from DOE/HQ and developed and submitted FY 87 taskassignments.

The SAIC licensing staff gave a presentation at DOE/OGR concerning the NNWSIProject licensing approach. The presentation provided OGR staff members withinformation about the issue resolution approach using position papers and toclarify requested funding levels in the FY 88 WPAS submittal.

WBS 1.2.5.2 LICENSING

WBS 1.2.5.2.1 Regulatory Interactions

Revision of the administrative procedure for NRC interactions continued at SAICbased on comments received from NNWSI Project participants and interactionswith WMPO staff representatives. Integration of the reporting requirementsincluded in the DOE/NRC Procedural Agreement (data reports, schedules, etc.)with the plans for development of the Information Management System (IMS) wasthe subject of several meetings during July and will be included in long-rangeplanning for compliance with the agreement. Planning for future NRCinteractions continued in support of WMPO integration activities.

At SNL records and input for the following laboratory tests were submitted tothe Data Records Management System: gas permeability, thermal dependence ofpermeability (saturated matrix), and unsaturated water-retentioncharacteristics.

SAIC personnel completed reviews and prepared comments on several NRC proposedregulations and guidance documents including the NRC proposed amendment tobring 10 CFR Part 60 into conformance with the EPA rule 40 CFR Part 191 and theborehole and shaft sealing generic technical position.

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Members of the Licensing Branch at SAIC undertook a detailed evaluation ofrepository boundary and area definitions. They made a comparison of therequirements of 10 CFR Part 60 with those found in equivalent regulations forother NRC fuel cycle facilities, including consideration of terminologyconsistency and technical basis for the definitions, and forwarded it to WMPO.The evaluation is currently being expanded for transmittal to WPO in August1986.

SAIC personnel finalized plans for the Licensing Process Briefings to be heldat USGS, Los Alamos, SNL, and LLNL on August 25-28, 1986. The briefings willlast approximately five hours at each location and will include presentationson the legal and procedural aspects of the licensing process.

The NNWSI Project Regulatory Document Manual is in final production forcontrolled distribution to WMPO and the NNWSI Project participants. Dependingon reproduction time requirements, distribution should commence in the secondhalf of August or early September 1986.

The SAIC Information Management group completed a review of the draft licensingsupport system procedures and specifications. Comments were forwarded to WMPOfor transmittal to DOE/HQ.

Representatives of the SAIC Information Management group attended a meeting inColumbus, with representatives of the Salt Repository Project (SRP) and DOE/HQto discuss the data base management system, (DM), and the SRP Integrated datamanagement system. Representatives of this group also attended a meeting inOak Ridge, Tennessee, with the DOE Office of Scientific and TechnicalInformation (OSTI) to discuss the data base management system in use at OSTI aswell as the information services available at OSTI.

SAIC staff members initiated procurement of the Information Management System(IMS) Bridge Program equipment during July. Requests for quotations fromqualified bidders should go out in early August with selection and purchaseorder execution scheduled for early September 1986. Delivery of the IMS BridgeProgram equipment is expected between early October and late November 1986.

Comments on the IMS Draft Concepts Evaluation report were received at SAIC fromComputer Services Corporation and LLNL. Responses to the comments wereprepared and forwarded to WPO for review.

WBS 1.2.5.2.2 Site Characterization Plan

The process for developing the SCP by December 31, 1986, has been streamlined.The Internal Review Committees (IRCs) have been modified to Permanent InternalReview Committees (PIRCs). It is the responsibility of the PIRCs to reviewvarious sections of the SCP and work with the original authors to provideresolutions to comments in a timely manner to meet the December deadline. Thetotal SCP will be reviewed by a Technical Overview Committee (TOC) after thevarious PIRCs have completed the first round ofcomment resolution.

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The first six PIRCs began reviewing the pertinent data on the design chapterwith the associated portions of Section 8.3. The status of each of these PIRCsections is as follows:

PIRC 1, Geology with Tectonics and Erosion. Distributed July 25; it isnow in review.

PIRC 2, Geoengineering with Rock Characteristics. Distributed July 17,and comment response forms (CRFs) sent to the chairman on July 29. Areview meeting is scheduled for August 1986.

PIRC 3, Hydrology with Ground-water Travel Time. Distributed July 28; itis now in review.

PIRC 4, Geochemistry with Dissolution and Systems Performance.Distributed July 17, and CRFs are due to the chairman by August 5, 1986.

PIRC 5, Meteorology and Climate. Distributed July 17. CRFs were receivedby the chairman on July 29 and a comment consolidation meeting was heldJuly 30-31. The comment resolution meeting is scheduled for August 11-13,1986.

PIRC 6, Repository Design with Seals. Sections 6.0, 6.1, and 6.2 weredistributed July 31; they are now in review. The remaining sections willbe distributed in mid-August 1986.

The remaining PIRCs (7 through 17) will begin to meet in August orSeptember 1986.

Chapters 2 (Geoengineering) and 4 (Geochemistry) were sent to DOE/HQ in lateJuly for release to the NRC and the State of Nevada for their information only.

SNL personnel submitted revised text for SCP Chapter 6 Sections 6.0, 6.1, and6.2 to SAIC on July 3. The revisions included resolution of comments from thereview by the Internal Review Committee as well as updates to accommodateguidance from DOE. Text for Sections 6.3 and 6.4 was submitted on July 25.Section 6.3 addresses specific topics called out in NRC Regulation Guide 4.17.Section 6.4 addresses the status of resolution of repository-design-relatedissues by describing the results of work already accomplished to resolve theseissues. Submission of references for Section 8.3 and updates for Chapter 6remain to be completed. Attention of SNL authors has now turned to preparationof remaining text for the RCD/SC. This text is expected to be completed bymid-August 1986.

USGS authors of the Site Characterization Plan, Chapter 3 (Hydrology) revisedor expanded sections for which they had primary responsibility to comply withcomments and recommendations made by the Internal Review Committee duringreview sessions on May 29-30 and June 4-5. The revised manuscript was sent toSAIC on July 8. Final illustrations, prepared in accordance with DOE styleguide requirements, were completed at USGS and mailed to SAIC on July 17.

SCP-related activities at SAIC in Golden during July included: (1) completionof the Chapter 8 reference and procedures lists; (2) completion of draftfigures for Chapter 8; (3) preparation and submittal to DOE of the Chapter 8

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CT*OS word processing disks; (4) updating of the SCP DATA-TRAC informationmanagement system files; (5) distribution of additional copies of the SCPChapter 8 draft to the USGS for Project internal review; (6) preparation of alist of proposed USGS Study Plans (based on the SCP Studies), grouped intocategories of completion schedule; (7) completion of the CT*OS word processingdocuments for SCP Chapters 1, 3, and 5.2 and submittal to SAIC in Las Vegas forproduction; and (8) a detailed review of Chapters 1, 3, and 5.2 for theupcoming reviews by the Permanent Internal Review Committee.

Other related activities at USGS included: (1) review and cost-savingrecommendations to the hydrologic prototype test plans; (2) preparation of theregulatory input to the site stratigraphy (prototype) scientific investigationplanning; and (3) development of an annotated outline and prototype example ofthe site stratigraphy Study Plan.

WBS 1.2.5.3 ENVIRONMENTAL COMPLIANCE

WBS 1.2.5.3.1 Environmental Assessment

In July, SAIC staff members reviewed the Environmental Assessment Administra-tive Record for completeness and updated it.

WBS 1.2.5.3.2 Environmental Impact Statement

Initial planning for the environmental impact statement EIS) support documentsis underway. The EIS scoping will be delayed until August 1987. No EISbaseline monitoring will occur until FY 88. The DOE/HQ EIS Implementation PlanWorking Document was reviewed at SAIC and comments were provided to WPO.

WBS 1.2.5.3.3 Environmental Regulatory Interactions

The draft Environmental Permit Plan was reviewed by WMPO and revised in July.The revised plan will be ready for review in August 1986. Preparation of thepermit applications continued during this report period.

SAIC staff members attended the DOE/HQ planning meeting on July 23-24 inSeattle to discuss the Environmental Monitoring and Mitigation Plan (EMMP)efforts. EMMP preparation continued in July.

Personnel at SAIC prepared a revised draft of the Issues Hierarchy Key Issue 3and sent it to the NNWSI Project Issues Hierarchy Working Group for review.They began work on the environmental study plans that will be needed in the SCPand preparation of the Environmental Program Plan that will explain how issuesand information needs will be resolved.

WBS 1.2.5.4 COMMUNICATION AND LIAISON

WBS 1.2.5.4.1 Institutional Studies

At SAIC, members of the institutional studies group initiated the developmentof background material relative to Consultation and Cooperation negotiations.

5-4

A preliminary draft of the Facility Specific NNWSI Project Outreach and PublicParticipation Plan for WMPO review is nearing completion. Additionally, staffmembers reviewed and commented on the OCRWM Policy Reader.

SAIC staff members attended the National Conference of State Legislatures'High-Level Radioactive Waste Working Group meeting in Denver on July 9. Thestatus of the program was reviewed and Nevada legislators raised a number ofissues with DOE/HQ OPA.

PROBLEM AREAS

The requirement for SNL personnel to use accrued annual leave prior toSeptember 30, 1986, combined with the commitment of a large part of the SNLstaff to the SCP effort, will result in the absence of many SCP authors duringAugust and September 1986. This may adversely affect the revision of SCP drafttext in response to review comments.

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NNWSIPERFORMANCE GRAPH FOR JUL 1986

WBS 1.2.5

Remarks: The cost variance is a result of a billing lag from the State of Nevada.

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U.S. DEPARTMENT OF ENERGYNNMSI PROJECT

For: JUL, 1986 Date: August 21, 1986

1.2.6 EXPLORATORY SHAFT INVESTIGATIONS

OBJECTIVE

The objective of this task is to identify and plan the tests that need to beconducted at the repository horizon as a part of detailed site characterizationand to design and construct the Exploratory Shaft (ES) and the underground testarea in Yucca Mountain. The primary focus of this effort will be to establishthe basis for evaluating the unsaturated zone in a welded tuff formation. Inaddition, an effort will be made to define the nature of the unsaturated zonewith regard to water content and water movement, and the nature of the naturalbarriers between the repository horizon and the static water level.

ACTIVITIES


SAIC representatives attended the exploratory shaft facility (ESF) committeemeeting to finalize the draft ESF subsystem design requirements; the draft wastransmitted to the architect-engineer.

SAIC personnel reviewed and provided comments on an assessment of the conceptof a centerline design borehole and mapping activities for the NNWSI ProjectESF and on the definition and pictorial representation of critical boundaries.

SAIC personnel completed a draft version of the WMPO ESF management structure,positional responsibilities, and participant organizational responsibilities.They also prepared an ESF architect-engineer study plan narratives andsubmitted them to WMPO and initiated an ESF Project procedure manual.

WBS 1.2.6.1.1 ES Management, Planning, and Design Review

Staff members at FS in Tulsa completed the draft FS Interface Control andCoordination Plan, began planning and assembly of the Title I Mock-up package,and completed a draft of the FS NNWSI Project Drafting Manual.

Personnel from WMPO, FS, H&N, REECo, SAIC,.and Los Alamos continued work onthe development of design criteria. A draft of the Design RequirementsDocument was submitted to WMPO on July 10. Following meeting with WMPO onJuly 14, the committee was disbanded.

H&N submitted a preliminary schedule of ESF Title I and Title II design toSAIC.

Representatives of HN gathered information for the Exploratory Shaft Test Plan(ESTP) Committee on the prototype testing completed in G-Tunnel and attendedthe ESTP Committee meeting in Dublin, California, July 24-25, where topics ofdiscussion included geologic mapping, DOE/HQ ESTP review comments, prototypetesting, chlorine-36, the SCP, and ESF design requirements.

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H&N and REECo personnel began to review the construction schedule and workorder outline for the exploratory shaft.

At a meeting held July 17 at WMPO to discuss quality assurance levelassignments, the possibility of assigning an interim QA Level of II to all ESFdesign work in order to permit design work to proceed was considered. However,the assignments in question became obsolete because the new ESF configurationcalls for a 12-ft-diameter shaft to the 1,484-ft depth, a 6-ft-diameter shaftto the 1,020-ft depth, a main test level at the 1,020-ft depth, and longdry-drilled exploratory coreholes.

Los Alamos staff completed rewriting the A procedures for ESF design reviewand control. The two procedures were updated and combined into one procedureentitled NNWSI Project ESF Design Control Procedure." This procedure willhave to be compatible with the interorganizational design interface controlprocedure being developed at WMPO and SAIC. Because the interorganizationalprocedure is not yet completed and approved, it may be necessary to modify theprocedure again in the near future. The interorganizational procedure cannotbe completed until (1) the scope of the procedure can be reexamined and (2) therole of the Nevada Test Site Office in the NNWSI Project is clarified.

Los Alamos personnel completed writing, word processing, and review of thedraft ESF subsystems design requirements (SDR) document. However, Appendix Bto the SDR is still being written. The document contains the criteria thatwill be followed by the architect and engineers in the design of the ESF. TheSDR was modified to reflect the decision by WMPO to change the ESF -configuration. The SDR document was hand carried to WMPO on July 21. Thedocument was a joint effort of WMPO, HN, FS, REECo, SAIC, and Los Alamos; itwill be issued as a WMPO document.

WBS 1.2.6.1.2 Safety and Quality Assurance

Two additional quality assurance level assignment (ALAS) sheets were preparedat USGS for Level 3 prototype testing for Geology by SAIC/Golden. A final copywas prepared and submitted to WMPO.

REECo QA personnel submitted a prepared action plan and response to WMPO Audit86-3 and conducted NNWSI-Project work sessions with field departments on plansand procedures.

Seven REECo QA procedures were submitted to WMPO for review on July 9.

The REECo QA requirements document for the exploratory shaft subcontract wasrevised and a copy was forwarded to WMPO.

WBS 1.2.6.2 SITE PREPARATION

WBS 1.2.6.2.1 Site and Roads

H&N personnel are developing departmental procedures for this task to complywith the HN QA Manual. Twenty-one procedures are presently in the internalreview process. The Materials Test Lab has completed drafts of all requiredprocedures and is compiling NNWSI Project applicable ASTM Standards.

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WBS 1.2.6.4 FIRST SHAFT

WBS 1.2.6.4.2 Hoist and Headframe

Staff members at FS in Tulsa completed ES-1 hoisting study requirements andconceptual arrangement.

WBS 1.2.6.6 SUBSURFACE EXCAVATIONS

At FS staff members completed a draft of the Controlled Blasting Study; it iscurrently under review.

WBS 1.2.6.7 UNDERGROUND SERVICE SYSTEMS

WBS 1.2.6.7.1 Utilities and Communications

F&S Tulsa personnel reviewed requirements for the ventilation, waste water,process water, and compressed air studies and investigated requirements for themine hoist electrical systems, mine communication system, and hoist signallingsystem.

WBS 1.2.6.9 TESTING

WBS 1.2.6.9.1. Exploratory Shaft Test Plan

QALAS for the SNL Exploratory Shaft Test Plan (ESTP) task were sent to WMPO forapproval.

The scientific investigation planning has been completed for LLNL exploratoryshaft investigations and is now being reviewed internally. Several draft QArequirements and procedures were reviewed and a draft position paper regardingQA requirements for NNWSI Project core samples was developed.

LLNL exploratory shaft personnel also reviewed SCP Chapter 2 in support of thePIRC activities.

USGS personnel prepared procedures for drift wall mapping, wrote a rationalefor continuous geologic mapping of the Exploratory Shaft (ES) and drifts,continued the writing of study plans for ES and drift tests, finished andsubmitted prototype investigation plans (PIPs), and presented the rationale forcontinuous geologic mapping of the ES and associated underground workings toWMPO.

All members of the shaft and drift mapping team participated in a one-weekexercise centered around the collection of required data from directionswritten by USGS geologists unfamiliar with the mapping requirements. Critiquesessions were held to further U.S. Bureau of Relcamation (USBR) knowledge indata collection and mapping techniques.

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USBR representatives met with VEXCEL personnel in Boulder on July 24 to discusscomputer modeling and a projected report on the subject. The possibility-ofsubstituting Rollei cameras for the far more expensive Hasselbiad cameras inthe drift wall stereomapping project was also discussed.

USGS, USBR, and LLNL representatives attended a presentation on continuousmapping of fractures and geology in the exploratory shaft and drifts. Thispresentation took place at the LLNL meeting of the ESTP committee on July 24-25in Dublin, California.

Cost estimates for prototype investigations were prepared by the ESTP PrincipalInvestigators (PIs) for in-house costs and by S for TS support. The firstworking draft of a schedule was developed by SNL. Los Alamos has prepared adraft recommendation for funding allocations to support essential tests andtest elements, but the participant organizations have not yet had anopportunity to review and comment before submiting the recommendations to DOE.

WBS 1.2.6.9.2 Exploratory Shaft Testing

WBS 1.2.6.9.2.3 Geomechanical Testing

At SNL work continued on Thermomechanics Analysis #6, which is being run insupport of the sequential drift mining experiment proposed for the exploratoryshaft. The calculations for the two-dimensional "elevation-view' analysis arecompleted and work began during July 1986 on the "plan view." This analysiswill be three dimensional to capture effects of the advancing excavation front.

Members of the SNL Applied Mechanics Division continued work on numericalsupport for the proposed plate-loading experiment in the exploratory shaft,Thermomechanics Analysis 9. Calculations using the compliant joint model wereinitiated as a continuation to this work.

WBS 1.2.6.9.2.4 Geochemical Testing

The diffusion test planned for the exploratory shaft facility (ESF) requiresprototype testing of the drilling techniques that will be used. A ScientificInvestigation Plan was prepared by Los Alamos staff for this activity andsubmitted for internal review. ALAS and criteria also were prepared for QAapproval.

The geochemical prototype test was discussed with FS and HN representativesat the Exploratory Shaft Test Plan Committee meeting in Dublin, California, onJuly 24 and 25. The purpose of the discussion was to provide sufficientdetails for an architect and engineer budget estimate.

WBS 1.2.6.9.2.5 Engineered Barrier Design Testing

LLNL personnel completed geophysical measurements at G-tunnel; a stop-workorder exemption for this activity was requested.

6-4

WBS 1.2.6.9.3 Integrated Data System

The fourth draft of the integrated data system document was provided by LosAlamos to the affected PIs, at the July 25 meeting of the ESTP Committee, witha request for comments and corrections. The undefined specifications formeasurement range, accuracy, and resolution are of particular concern.Comments from the PIs have not been received to date.

WBS 1.2.6.9.4 Prototype Testing

Representatives from FS, Los Alamos, REECo, and H&N met to develop theestimate and schedule for the Prototype Testing Program at -Tunnel.

On July 31, HN, FS, and Los Alamos personnel met to determine HN surveyrequirements and costs for the prototype test program.

WBS 1.2.6.9.4.1 Prototype Geologic Testing

U.S. Bureau of Reclamation (USBR) staff members updated and rewrote thePrototype Investigation Plans (PIPs) as a result of the field work accomplishedduring the site visit by the mapping team the week of July 14-18.

WBS 1.2.6.9.4.2 Prototype Hydrologic Testing

USBR PIPs were written and presented to Los Alamos for review. These PIPs arenow being edited and revised to incorporate new ideas and will be completed andresubmitted for review in early August 1986.

USBR staff members are identifying specific prototype testing instrumentationneeds to be incorporated into a data acquisition requirement summary asrequested by Los Alamos.

PLANNED WORK

Los Alamos staff members will complete the prototype test analyses and, afterparticipant review , present the findings and recommendations to DOE. They willcontinue to obtain consultant agreements with the eight to nine technical peerscontacted as candidates to review the ESTP Revision 1 document.

A Los Alamos draft study plan for the chlorine-36 Water Movement Tracer Testwill be prepared in collaboration with SAIC.

PROBLEM AREAS

The FS Tulsa design effort is currently not meeting the baseline schedule setforth in the Project Management Plan; this schedule was based on receivingcomplete design requirements documentation on June 25. A revision to theexisting schedule cannot be made until the draft ESF subsystem designrequirements document has been evaluated to identify any additional work andthe time impact of special studies has been evaluated.

6-5

H&N received direction from DOE to proceed with the ESF conceptual design andspecial studies. Because a Quality Level II has currently been assigned to allESF design, HN cannot initiate any design work until procedures have beenapproved. A list of special studies is forthcoming from WMPO, but it is notclear at this time what quality level these studies are to be performed under.

Los Alamos is still experiencing difficulty in getting appropriate requirementsdefinitions from the PIs. Numbers and types of instruments, range, accuracy,and resolution are some of the unknowns. In addition, exploratory shaftfacility design information is not available in some cases. As a result, thetechnical chapters of the requirements document will often include the phrase"to be determined."

6-6


WBS: 1.2.6

Remarks: The cost underrun and behind-schedule conditions arepreparation and approval of QALAS taking longer than planned andprocedures not being completed.

attributed tointerface control

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1.2.7 TEST FACILITIES

OBJECTIVE

The major objective of this task is the design, construction, and operation ofthe test facilities that support technology development for other wastemanagement programs and other geologic repository projects. The two majorfacilities operated under this WBS element are the Climax Spent Fuel TestFacility and the E-MAD Facility.

ACTIVITIES

WBS 1.2.7.2 TESTING

WBS 1.2.7.2.1 Climax

WMPO requested HN to submit an estimate for a prefabricated metal building toreplace the existing wood construction pile driver hoist house in Area 15.

WBS 1.2.7.2.2 E-MAD

Westinghouse personnel performed the final inspection of the five radiationshield windows stored in the east process cell. The window assemblies are in adeactivation storage mode. Other activities included final inspection of thestack air monitoring system and shut down of the equipment in accordance withthe Deactivation Plan and final inspection and shut down of the Constant AirMonitor (CAM) equipment in accordance with the Shutdown Plan.

Westinghouse staff members deactivated and disassembled the calorimeter systemfor a shipment to Idaho National Engineering Laboratory. Decontaminationefforts have been successful to prepare the vessel for shipping. Master SlaveManipulators are being deactivated in the main disassembly bay.

Westinghouse quality assurance staff members continued to review and verifyquality records. Fourteen more boxes are ready for shipment to the recordslibrary. Verification and indexing of remaining records is continuing.

The terminal condition of the E-MAD Facility Spent Fuel Dry StorageDemonstrat ion Test Location is in final review by Westinghouse personnel. Thedocument will be completed by August 8, 1986.

WBS 1.2.7.2.3 G-Tunnel

The HN survey group worked in U12G in support of USGS mapping lowerextensometer drift. No further survey work in support of the NNWSI Projectwill be performed in -Tunnel without written authorization from WMPO/NTSO.

7-1

COST

NNWSI PROJECTCOST PERFORMANCE GRAPH FOR JUL 1986WBS:1.2.7

1.2.8 LAND ACQUISITION

OBJECTIVE

The objective of this task is to maintain access to LAnd adjacent to the Nevada

Test Site that is controlled by the U.S. Air Force and the Bureau of Land

Management and to protect land that could be used for a high-level waste

repository and the surrounding buffer zones.

ACTIVITIES

None to report.

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1.2.9 PROJECT MANAGEMENT

OBJECTIVE

The objective of this task is to manage all activities of the NNWSI Project byall participants. The five major areas identified are Project Management,Project Control, Interface Activities, Quality Assurance, and GenericRequirements Document (GRD) Support.

ACTIVITIES


WBS 1.2.9.1.1 Management

Plans are in progress for T&MSS to occupy additional space on the 5th floor ofthe Valley Bank Center building. Occupancy is scheduled to take place in lateSeptember 1986.

The Exploratory Shaft Project Management Plan (ESPMP) draft Revision 1 was sentto the revision task group for review on June 16, 1986. Organizationalquestions still remain to be resolved during the review process. Comments weredue to SAIC on July 30.

The draft NNWSI Project Management Plan (PMP) was issued for WMPO and NNWSIProject review on June 26, 1986. A presentation was made to WMPO staff memberson July 15 to explain the PMP contents. Comments have been received from SAIC,REECo, F&S, HN, and Los Alamos. Comments were due to SAIC on July 30.

The latest revised cost estimates (LREs) for the TMSS FY 86 task plans weredeveloped at SAIC and sent to WMPO. Work on TMSS Y 86 task plans is completeand preliminary development of the FY 87 task plans began.

Members of the Computer Support Services Branch at SAIC installed 64 mb ofmemory on the VAX 11/785. The 52 mb-increase has resulted in a significantperformance increase.

F&S personnel participated on the committee that prepared the ESF DesignRequirements Document for WPO, participated in discussions with REECorepresentatives on the hoisting study draft and proposed layout of ES-1, andreviewed QA design control procedures that will be used in the FS Tulsa ESFdesign effort.

The NNWSI Project IBM/PC with software for indexing records was installed atF&S at the Nevada Test Site. Some training of FS records management staffmembers was conducted.

F&S personnel issued a draft estimate to Los Alamos for the Prototype TestingProgram at G-Tunnel.

9-1

At LLNL a review of current work activities resulted in a letter to WMPOrequesting exemption of several activities from the stop-work order.

LLNL personnel expended considerable effort on reviewing and assessing thestop-work order implications and resolutions. The LLNL FY 86 budget wasreviewed with the stop-work order implications in mind. A revised underrunestimate was submitted to SAIC and WMPO with a request for FY 87 carryover.The FY 87 budget was reviewed and a baseline budget to the third-level WBS wassent to SAIC.

The permanent Technical Project Officer Dave Harris, for the USBR, reported forduty on July 28.

WBS 1.2.9.1.4 Records Management

The Quality Records Management Committee met on July 17, 1986, at the SAICoffices in Las Vegas, Nevada. All NNWSI Project participants are in theprocess of developing records management system plans and technical procedures;however, these documents cannot be finalized until the NNWSI Project recordsmanagement SOP-17-01 is approved. This standard operating procedure ispresently in review as a part of the approval process. Also discussed at thismeeting was the retrofit schedule and records protection during processing.The latest version of the QRMS Data Base User's Guide was distributed anddiscussed.

The USGS document-type list now reflects most of the USGS records types for theNNWSI Project. Additions to this list of new types will be made as necessaryin the course of records collection. The feasibility of doing the microfilmfunction at the USGS is receiving continued attention.

A representative of Effective Solutions, Inc., visited the USGS records centerto install additional segments of the customized REVELATION software upgradeand to train the records center staff in its use. This upgrade reflectsrevisions to the plan for transmittal of records to the Project Records Centerwherein hard copies will be sent to HN at Mercury to be microfilmed and theassociated computer index information will be sent to the DOE contractors inLas Vegas for processing. SAIC personnel installed the REVELATION software onREECo's IBM PC on July 15. A REECo Records Management employee was theninstructed in the use of the software and the indexing of QA documents.

Project personnel attended the first phase of the Quality Records ManagementSystem (QRMS) training conducted by Effective Solutions, Inc., (ESI) at SAIC onJune 30-July 2. Specific instructions were received regarding implementingprocedures for the receipt and processing of QA records for transmittal to theNNWSI Project Microfilming and Archival Storage Service Facility. The dutiesand responsibilities of the.records administrator and the Project recordscenter staff were also defined.

The data base for the QRMS was installed in the IBM computers at H&N andinitial training on the software was conducted. Further training will bescheduled in August.

9-2

Development of procedure information for the REECo Quality Assurance RecordManagement Handbook was completed and submitted to QA. This information waslater condensed into Technical Project Office Procedure No. TPO-1, DocumentDistribution Control." It is being forwarded to WMPO for review.

At the direction of the Nevada Test Site Office, REECo approved funding forengineering estimates on USGS requested renovationns at Test Cell C."

REECo personnel worked with NNWSI Project staff on the proposed work orderoutline for the exploratory shaft referencing appropriate WS reportingelements.

WBS 1.2.9.2 PROJECT CONTROL

SAIC Planning and Scheduling staff members began incorporating input from theNNWSI Project participants into issue-oriented networks for the SCP. They alsoprepared and sent out for participants' review and comments a list of NNWSIProject priorities. A new network, Environmental Permitting Schedule, wascreated for inclusion in the Environmental Permitting Plan.

The NNWSI Project fiscal year at completion is estimated at 15,723,900compared to the baselined budget of 17,523,900. This amounts to a variance atcompletion of 1,800,000. A letter identifying the mark-up and distribution ofthe underrun will be completed in August 1986.

Explanations of SAIC schedule and cost variances that exceed the 10 percentthreshold follow:

WBS 1.2.1 Cost Variance--underrrun 12.02 percent. Unable to completeanticipated manpower staffing. A budgeted subcontract was determined notto be necessary.

WBS 1.2.3 Cost Variance--underrun 11.94 percent -- Behind schedulevariance 12.49 percent. Personnel were not available to complete requiredactivities. Delays were experienced in the Air Force overflight studydraft report and the Population Density report.

WBS 1.2.4 Cost Variance--Underrun 18.97 percent. Difficulty and delay infilling two staff positions.

WBS 1.2.5 Behind schedule variance 10.87 percent. Absence of NRCinteraction and diversion of resources to other activities. RegulatoryCompliance Plan and draft Regulatory Document Manual delayed awaitingadditional information from DOE. SCP delivery date slipped due to changein review process.

All replanning data received by SAIC was input into the CSPEC system to showreplanning of latest revised estimates and to provide Project replanningfigures with variances to the baselined budget for Level 4 WBS and Level 3 WBSsummaries.

SAIC staff members completed the coordinated performance measurement datasystem (PMDS) data input and output of NNWSI Project latest revised estimatesand completion variance data for FY 86. They also completed a draft NNWSIProject PMDS data requirements document.

9-3

Personnel at SAIC completed and submitted to DOE/RMBD a draft Budget Data EntrySystem (BDES) Test Plan along with a Functional Test Record Log to record inputof test data for the BDES. The BDES Test Plan incorporated WMPO/RMBD revisionrequirements. The dummy test data was input and transmitted to DOE/HQ.

The capital equipment report for FY 86 for SAIC was completed and transmittedto DOE/RMBD. Personnel from the SAIC Cost Schedue and Control Branchcompleted a cost estimate checklist for WMPO for exploratory shaft constructionestimates. They also began development of a capital equipment tracking systemfor anticipated DOE requirements.

Efforts to get the USGS back to work include: (1) preparation of justificationfor prototype testing and ongoing activities, (2) development of data basefiles, (3) correlation of USGS activities to issued reports, (4) preparation ofWBS dictionary forms for new tasks, (5) generation of a work resumptionschedule, (6) submittal of a list of study plans to SAIC/Las Vegas and(7) submittal of a list of ongoing activities at Menlo Park to SAIC in LasVegas.

An optimistic procedure for preparation of scientific investigation planspotentially supports the resumption of USGS activities in early FY 87.Preparation of the plans incorporates computer-aided sorting of SCPinformation, manual development of SCP-based and WBS-based interfaces, andtraining support of quality assurance level assignments to prepare a roughdraft for guidance to the principal investigators.

Preliminary drafts have been initiated by SAIC/Golden for scientificinvestigations classified as necessary to prevent irrecoverable loss ofinformation. These include the seismic network operations, streamflowmonitoring activities, and Fortymile Wash activities scheduled to begin beforethe SCP is issued. A draft has also been prepared for exploratory shaftgeologic testing.

An exploratory shaft prototype investigation plan schedule was developed atUSGS for hydrologic testing. This schedule evolved in conjunction withinformation provided from the BOR software system.

Considerable effort continues to be expended at USGS in an attempt to resolvethe confusion concerning the milestone list. Independent and uncoordinatedidentification of milestones by DOE, SAIC/Las Vegas, and in the SCP resulted ina serious discontinuity between upper level milestones recognized by the USGSand in the milestone data base. To reduce the confusion, a baseline set ofmilestones has been prepared by SAIC/Golden on the basis of the work plans andinput from the FY 88 budget. The list will be updated according to thestop-work order and distributed to the USGS management staff for review andmodification.

WBS 1.2.9.3 QUALITY ASSURANCE

Revision 3 to the TMSS QAPP and supporting documents, including qualityprocedures, administrative procedures, corporate policies, and SAIC corporatepurchasing instructions, was submitted to WMPO on July 15. The revisionincludes the changes necessary to affect the corrective actions made as a

9-4

result of the TMSS response to NNWSI Project Audit 85-15 and Revision 4 of theNNWSI Project Quality Assurance Plan, support SOPs, and interim changes to thePlan.

The quality assurance (QA) training status report has been updated from themanagement information and committment control data base to track all NNWSIProject personnel QA level assignments, responsibilities, orientation andindoctrination dates, any technical training accomplished, the date of the lastproficiency review (for quality Level 1 work activities), as well as homeoffice location. Inputs have been received by task managers and are beingincorporated into the report. A list of personnel requiring training is indevelopment with training to be conducted in August 1986. Update of the QAtraining status report continues.

At SAIC corrective action in response to the WMPO nonconformance order toprevent recurrence was completed on July 18, 1986. No response has beenreceived to date.

SAIC staff members prepared FY 87 preliminary task plans and budget estimatesbased on the WPAS output. They also attended the DOE/HQ Quality AssuranceCoordination Group (ACG) meeting held in Denver on July 23-24 and provided thegroup with a document containing suggested standard A definitions to be usedby all the projects for uniformity.

Four audits have been conducted to date as scheduled in FY 86. The auditschedule was revised on July 21. The following organizations and NTScontractor audits have been postponed until further notice: Los Alamos, WMPO,H&N, SNL, and SAIC/T&MSS. The schedule changes were due to the stop-work orderissued by WMPO to the participating organizations on June 9-10, 1986.

Of the 15 audits conducted in FY 85, 8 audits remain open. However, additionalcorrective actions to findings have been implemented and verified by WMPO.

As a result of the stop-work orders issued to all NNWSI Project participants,activities for surveillances in July were limited and only five surveillanceswere conducted during the month: LLNL, in Livermore, CA, and at G-Tunnel onthe Nevada Test Site; SAIC, Nevada Test Site; USGS, Nevada Test Site; and FSin Tulsa, OK. A total of 46 surveillances have been conducted in FY 86 and 214items or activities monitored. During this effort, 31 NCRs have been recorded.

Comments from the formal review of the draft NNWSI Project-SOP-17-01 are beingresolved and changes are being incorporated. Final approval and issuance ofNNWSI Project-SOP-17-01 is projected for late August 1986.

The QA Records Management System is installed and operational at allparticipating organizations, NTS support contractors, WMPO, the Microfilmingand Archival Storage and Service Facility, and the NNWSI Project RecordsCenter. Final training and debugging will be conducted during August andSeptember 1986.

The Quality Assurance Records Management Committee met to discuss the statusand completion of the QA records management system installation, the temporarystorage of QA records during processing, the microfilming of QA records, andthe retrofit schedule for collection and indexing of backlogged QA records.

9-5

Revisions to QA Plan NVO-196-17 and its supporting procedures are in progressand substantial changes to improve clarity and useability are being made. Thecompletion date of July 31 for the draft was not met due to support given toother priority tasks. The draft revisions of these documents should becompleted during August 1986.

The delay in changes to NVO-196-18 and the related implementing procedures hasbeen severely impacted by review and coordination of USGS submittals (insupport of their activities to be continued during the stop-work order) and thesubmittal of the revised USGS Quality Assurance Program Plan (QAPP). Revisionand issuance of NVO-196-18 and its MPs is projected to be completed on orbefore September 30, 1986.

Significant effort has been expended by SAIC staff members in support of theUSGS A program. Current activities include quality level assignments andsubmittal of Site Investigation Plans (SIPs). It is anticipated that the workload for the USGS support will increase.

The USGS Quality Assurance Program Plan (QAPP) and implementing A procedureswere submitted to WMPO for formal review and approval on July 17. Review ofthe documents has begun and should be completed by the end of August 1986.

USGS submitted a list of 32 activities which were necessary to continue underthe stop-work order. A review of the activities and the submittals to supporttheir justification for continuance was conducted by WMPO and QASC personnel onJuly 21-23. Of the 32 activities listed, 9 were judged to meet the exemptioncriteria outlined in the WMPO stop-work letter. A summary letter has beengenerated for submittal to USGS.

SAIC personnel have provided full-time support to the task force appointed byWMPO to investigate the problems at the USGS Core Sample Library. The taskforce report to the Core Library Steering Committee was completed on July 30.The Steering Committee Interim Report to WMPO will be completed within twoweeks. Preliminary findings include many deficiencies, both programmatic andperformance. The impact of the findings is unknown at this time. Another taskforce was organized to develop recommended core sample procedures that wouldprovide traceability and integrate onsite inspection meeting QA requirements.The results of this effort will be reported to the Steering Committee at thenext meeting.

A NNWSI Project committee to determine QA requirements for auxiliary softwarehas been established. The first meeting was held on July 22 in Las Vegas. Thecommittee will revise SOP-03-02 to include all software. Significant progresswas made during the meeting and it is anticipated that the task will becompleted with a minimum number of meetings. The next meeting of the committeewill be September 3, 1986, at the USGS Western Region Headquarters in MenloPark.

Efforts continue at SAIC to process Los Alamos SIPs and quality assurance levelassignment sheets. Those for Mineralogy and Petrology work were approved forimplementation on July 17. Those for the exploratory shaft facility (ESF) andthe integrated data system (IDS) were returned with comments. Other Los Alamosdocuments currently being reviewed include the site investigations planningdocumentation and quality level assignments for microbiology, tectonics and

9-6

volcanism, prototype air coring, and the exploratory shaft test plan. ThreeLos Alamos quality procedures were approved and four additional procedures arein the review cycle. In addition, a letter in reply to the work directivedetails the Los Alamos activities that are authorized to proceed as exemptionsto the stop-work directive. Another meeting was held in Los Alamos on July 23to discuss comments related to the QA level assignments for the IDS and toreview quality program requirements relative to procurement activities. LosAlamos agreed to assign a QA level to the design phase of the IDS and follow-upwith revised quality assurance level assignments for individual items of thesystem.

SAIC support of LLNL continues with the review of three procedures on recordsagainst SOP-17-01, which is in preparation. Comments were reviewed with LLNLon July 7. Official review of this document is held in abeyance untilSOP-17-01 is approved and released. QA personnel visited LLNL on July 28 and29 to review Sections 4, 7, and 1 of the LLNL QAP.

A review by SAIC personnel of the SNL QAPP was completed. The QAPP was foundto be deficient in meeting the requirements of SOP-02-01. A meeting was heldat SNL on July 6-8 with a WMPO representative to discuss the comments. SAICstaff members spent the week of July 25 at SNL to assist with the resolution ofthe SNL response to WMPO comments. Several comments remain to be resolved byWMPO. Current efforts are directed toward review of the SNL QAPP and APs andthe review and approval of SNL quality assurance level assignments. To date,15 sets of scientific investigation planning documentation and associated QAlevel assignments have been approved.

The FS APP and AP submitted in April 1986 is under review at SAIC. SAICQASC staff members participated in a surveillance of FS (Tulsa) on July 24-25.The surveillance was focused on design activities to determine the FS state ofpreparedness to perform subsurface design of the ESF. A review of designprocedures, personnel certifications, training records, and organizationalcharts was completed. FS appears to be prepared to undertake design of theESF from their Tulsa office.

SAIC QA members presented training sessions on scientific investigationplanning and QA level assignments to the Site Integration Group on July 2 and7. A training session, "Introduction to Quality Assurance Auditing," wasconducted on July 23-24. Twenty-five attendees included eleven NTS supportcontractor personnel, five from the laboratories, eight from TSS, and onefrom SAIC.

Members of the QASC staff attended the SCP-CDR Q-List Methodology Workshop atSAIC on July 15-16. Members of DOE/HQ, SNL, SAIC Licensing Branch, and Bechtelwere also present. DOE/HQ and the NNWSI Project participants exchangedinformation regarding approaches to the development of the SCP-CDR Q-List.

A APP specific to the SNL NNWSI Project (Milestone R088) was submitted to WMPOfor approval on May 29, 1986. On July 7-8, 1986, WMPO and SAIC representatives.visited SNL with WMPO review comments. Discussions led to an agreement toapprove the QAPP by sections. At the end of July 986, 9 of the 18 sections ofthe QAPP were awaiting final WMPO approval.

9-7

quality assurance level assignment sheets and modified work plan packages for50 of 53 WS tasks assigned to SNL were submitted to WMPO for approval (3 havebeen deferred). Approvals have been obtained for 22 of the WBS tasks. In aneffort to develop and gain approval for quality assurance procedures necessaryto implement the policies nd practices called for in the APP, 37 qualityassurance procedures were identified as needed, 14 are in draft form ininternal review, and 4 have been submitted for WMPO approval.

Three LLNL procedures for procurement document control, for control ofpurchased materials, parts, and components, and for nonconformances weresubmitted on July 2 for WMPO review and approval.

LLNL personnel reassigned levels of quality assurance to exploratory shaftactivities in preparation for submittal of a Scientific Investigation Plan toWMPO. Twelve activities had been originally assigned levels on January 17,1986, but changes in SOP-02-02 resulted in a total of eight activities beingassigned levels of quality assurance.

Revision I of the HN NNWSI Project amendments to the A Manual was submittedto WMPO for approval.

H&N requested exemption from WMPO from the requirement to maintain duplicatecalibration records, which are already maintained by REECo and EG&G. Responsehas not been received.

A letter was submitted to WMPO requesting confirmation that HN would not berequired to submit QA administrative procedures to WMPO for review.Confirmation has not yet been received.

PLANNED WORK

Development of the T&MSS A orientation and indoctrination training videotapesshould be completed for final review and release in early August 1986.

At SNL work will continue on the filing of records, the detailed development oftechnical procedures during this initial indexing phase, and the developmentand refinement of the Records Management Plan and the records managementprocedure AP 17-04.

Two proposals for activities related to waste package design will be evaluatedat LLNL through the month of August and a contract should be placed bySeptember.

Work is progressing well at SAIC/Golden on preparation of the QA Manual for theUSSR to cover the Bureau's work for the USGS. This task cannot be completeduntil the USGS manual, currently under review by WMPO, is approved.

Internal Los Alamos audit findings have been closed for several audits heldearlier in this fiscal year. This is a first-priority activity in the transferof the quality assurance support function to a contractor. Los AlamosTechnical Associates (LATA) has signed a contract to provide A support andwill begin formal transition activities on August 15.

9-8

Los Alamos received WMPO approval for three QA procedures covering surveil-lance, calibration, and assignment of quality levels. Four other QA procedureswere distributed for review and comment in preparation for a writing andconcurrence session early in August. The procedures will deal with SupplierQualification (QP-22), Audits (QP-17), A Training (QP-20), and CorrectiveActions (QP-21).

PROBLEM AREAS

Still at issue is how to make quality level assignments to exploratory shaftfacility design elements, items, and activities. A July 17 meeting betweenWMPO and Los Alamos failed to resolve this issue.

MILESTONE PROGRESS

Preparation of the plan to implement an SNL records management system(Milestone R087) is delayed and awaiting approval of SOP-17-01.

9-9

COSTNNWSI PROJECT

PERFORMANCE GRAPH FOR JUL 1986WBS:1.2.9



PARTICIPANT

BUDGET vs COST

COST PERFORMANCE REPORT - LEVEL 3WORK BREAKDOWN STRUCTURE (FORMAT 1)


COST PERFORMANCE REPORT -LEVEL 4WORK BREAKDOWN STRUCTURE (FORMAT 11


COST PERFORMANCE REPORT -LEVEL 4WORK BREAKDOWN STRUCTURE (FORMAT 1



WBS: 1.2.A

10-4


WBS: 1.2.B

Remarks: Cost variance due to comparison of actual costs to aas per instruction from DOE/HQ. straight-line budget

10-5

.


WBS:1.2.E

Remarks: Cost variance due to comparison of actual costs to a straight-line budgetas per instruction from DOE/HQ.

10-6


WBS: 1.2.F


10-7


WBS: 1.2.G1986

Remarks: To date the USGS has submitted earned value data only one time. Therefore,BCWP ACWP = BCWS. As a result, this distorts the status of the USGS work.

10-8


WBS: 1.2.H

Remarks: Cost variance due to comparison of actual costs to a straight-line budgetas per instruction from OE/HQ.

10-9


WBS:1.2. I


10-10


WBS: 1.2.L

Remarks: Variances within the threshold of 10 percent. No analysis required.

10-11


WBS:1.2.N

Remarks: Cost variance due to billing lag and the comparison ofa straight-line budget as per instructions from DOE/HQ.

actual costs to

10-12


WBS: 1.2.P

10-13


WBS:1.2.R

Remarks: Cost variance due to comparison of actual costs to a straight-line budgetas per instruction from DOE/HQ and drilling work delay at site.

10-14


WBS: 1.2.S

Remarks : .The primary reasons for the cost underrunsubcontracts and a reduction in the cost of labor.

Current

. NNWSI PROJECTCOST PERFORMANCE GRAPH FOR JUL 1986

WBS:1.2.T

Remarks: The cost underrun is due to staffing restraints and a reduction in thecost per delivered hour.

10-16


WBS:1.2.U

Remarks: Cost variances due to comparison of actualas per instruction from DOE/HQ.

1O-17


WBS: 1.2.X1 986

10-18

July 1986

MilLESTONE DESCRIPTION

LEVELNEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS

I MILESTONES IN A TIME WINDOW OF 1 Oct 1985 TO 30 Sep 1986Run Date: 4 August 1986

July 1986 NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONSLEVEL 1 MILESTONES IN A TIME WINDOW OF 1 Oct 1985 TO 30 Sep 1986

Run Date: 4 August 1986

MILESTONE DESCRIPTION

Report on Geochemistry simulation ofYucca Mountain Using Best AvailableData on Mineralogy. Water Chemistry,Flow Rates and Crack Statistics

Implementation of MeteorologicalMonitoring Plan

Final Radiological Monitoring PlanComplete

Draft Socioeconomic Monitoring endMitigation Plan

Review of the Concepts Developed byHEDL for Remote/Automated WasteHandling Systems Initiated

Asistance to EDL in DefiningRemote/Automated Waste HandlingSystems

Start Repository Advanced ConceptualDesign

Initial Subsystem Design Requirement(SDR)

Report on G-Tunnel UndergroundFacility (GTUF) Summary

Feasibility Analysis of HorizontalEmplacement and Retrieval - LetterReport

July 1986 NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONSLEVEL 1 MILESTONES IN A TIME WINDOW OF 1 Oct 1985 TO 30 Sep 1986

Run Date: 4 August 1986

MILESTONE DESCRIPTION WBS NO.

Horizontal Waste EmplacementEquipment Development Pn

Prepare Design Requirements andMaterials Recommendation Report

Preliminary Study of the Effects ofUncertain Geologic Data on Design ofthe Underground Facility

Issue IMS Requirement Study toWMPO/NV for Review and Comment

Draft Site Characterization Plan(SCP)

Camera Ready EnvironmentalAssessment/Comment Response Appendix(EA/CRA) to DOE/HQ

ESf Shaft and Mining SubcontractAwarded

Complete Exploratory Shaft ReadinessReview

Start First Shaft (ES-1) Construction

Start ESF Site Preparation

1.2.4.2.2.1.S

1.2.4.2.3.1.S

July 1986

NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONSLEVEL 1 MILESTONES IN A TIME WINDOW OF

1 OCT 1985 TO 30 SEP 1986RUN DATE: 4 AUGUST 1986

NNWSI PROJECT STAFFING*FISCAL YEAR 1986

BUDGET ACTUAL VARIANCE700

*These budgeted and actual amounts reflect Input from six project participants.Los Alamos,

PLANNED NNWSI PROJECT FIELD ACTIVITIES

FOR SEPTEMBER

PlannedParticipant Activity Location Day

L86-PMSD-JHF-189

September 26, 1986

SCIENCE APPLICATIONS INTERNATIONAL CORPORATIONTO: Distribution

SUBJECT: September 1986 PM-TPO Meeting (October 1-2)L86-PMSD-JHF-189

Enclosed is an agenda for the September Project Manager-Technical ProjectOfficers meeting which will be held on October 1-2 in Room 450 at SAIC,101 Convention Center Drive (Valley Bank Center). Please note that this willbe a two-day meeting.

Any changes to the Agenda will be posted and discussed during the meeting.

SCIENCE APPLICATIONSINTERNATIONAL CORPORATION

JOY H. FIORE,ManagerPROJECT SERVICES Branch

JHF:bp

Enclosure:Agenda

Valley Bank Center, 101 Convention Center Drive, Suite 407, Las Vegas, Nevada 89109, (702) 295-1204Technical Management Support Services Contractor Nevada Nuclear Waste Storage Investigations

AGENDA N-AD-028NNWSI PROJECT MANAGER-TECHNICAL PROJECT OFFICER MEETING

LOCATION: 101 Convention Center Drive

Las Vegas, Nevada DATE: 25-Sep-86

AGENDA N-AD-028NNWSI PROJECT MANAGER-TECHNICAL PROJECT OFFICER MEETING 6/86

LOCATion: 101 Convention Center Drive PAGE 2 of 4


Tom/ Don/ TPOs

Jim B./Don

NNWSI PROJECT MANAGER-TECHNICAL PROJECT OFFICER MEETING 6/86LOCATION 101 Convention Center Drive PAGE: 3 of 4


AGENDA N-AD-028NNWSI PROJECT MANAGER-TECHNICAL PROJECT OFFICER MEETING 6/86

LOCATION 101 Convention Center Drive PAGED 4 of 4



NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECTNRC INTERACTIONS

STATUS

o HEADQUARTERS, SLQA DIVISION, PLANS TO MEET WITH NRC TO ESTABLISH"GROUND RULES" FOR PROJECT/NRC MEETINGS.

o AT LEAST 30-45 DAYS PREDICTED UNTIL MEETINGS CAN BE SCHEDULED.MID-NOVEMBER APPEARS THE EARLIEST TIME, BUT DECEMBER MORE LIKELY.

o ALL MEETINGS MUST NOW GO ON HOLD.

o A LETTER SEEKING TPO COMMITMENTS ON THE COMPLETION OF PREREQUISITES WENTTO WMPO ON SEPTEMBER 16, 1986.

7 DMD 10/2/86


NEVADA NUCLEARWASTESTORAGEINVESTIGATIONSPROJECTNRC INTERACTIONS

CLOSURE OF OPEN ITEMS

o LETTER TO HUNTER REQUESTING COMMITMENT TO CLOSE THREE ESF DESIGN ANDCONSTRUCTION OPEN ITEMS SENT SEPTEMBER 22, 1986.

o LETTER TO OAKLEY REQUESTING INPUT TO CLOSE TWO ESF DESIGN ANDCONSTRUCTION OPEN ITEMS SENT SEPTEMBER 25, 1986.

8 DMD 10/2/86

U.S. DEPARTMENT O ENERGY

NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECTNRC-INTERACTIONS

SEISMIC/TECTONIC TECHNICAL MEETING

0 ORIGINAL-INFORMAL-SCHEDULE NOVEMBER 3/4

o NNWSI PROJECT PROPOSED RESCHEDULE TO NOVEMBER 10/11

o NRC WANTS MEETING AFTER DECEMBER 1

o ON HOLD DE TO HQ/SLQA

o NNWSI PROJECT PRELIMINARY MEETING WITH DOE/HQ SCHEDULED FOR OCTOBER15/16. LOCATION UNCERTAIN. NEED SPECIFIC DOE/HQ PARTICIPATION.

0 NEED TO KEEP MOMENTUM

9 DMD 10/2 86



NRC INTERACTIONS

APPENDIX 7 MEETINGS

USGS, AUGUST 26-27, 1986 - DENVER

STRUCTURE AND TECTONICSGEOPHYSICSCALCITE-SILICA DEPOSITS

10 DMD 10/2/86



NRC INTERACTIONS

PROPOSED AGREEMENT APPENDIX 8 VISITS TO PROJECTS

o PROVIDES FOR VISITS BY PERSONNEL OTHER THAN ON-SITE REPRESENTATIVE

o CONDUCTED FOR INFORMATION TRANSFER AND WHEN EXPERTISE OF STAFF OTHER THANOR IS ESSENTIAL TO MAKE NECESSARY OBSERVATIONS

EXAMPLES: - OBSERVATION OF SPECIALIZED TESTING- INSPECTION OF GEOLOGIC FORMATIONS- INSPECTION OF PATH OR TEST SPECIMENS

o NOT FOR DELIBERATIVE DISCUSSIONS OR AGREEMENTS

EXAMPLES: - DISCUSSIONS CONCERNING VALIDITY OF DATA, INTERPRETATIONSOF DATA OR REGULATIONS, METHODS OR PROCEDURES FOR TESTSOR ANALYSES FUTURE TEST PLANS OR AGENCY POSITIONS

- PRELIMINARY IDENTIFICATION OF POTENTIAL LICENSING ISSUESPRELIMINARY COMMENT ON MERITS OR DIRECTION OF DOEACTIVITIES

11 DMD 10/2/86


Nevada

NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECT

NRC INTERACTIONS

APPENDIX 8 CONTINUED

o NRC QA AUDIT OBSERVERS MAY DOCUMENT OBSERVATIONS AFTER LEAVING THE AUDITSITE, CONTRARY TO OTHER APPENDIX 8, TECHNICAL MEETING, AND MANAGEMENTDOCUMENTATION PROCEDURES

o NRC STAFF OTHER THAN THE OR AND CONTRACTORS MAY REQUEST PERMISSION TOATTEND DOE MEETINGS BEING ATTENDED BY THE OR UNDER APPENDIX 7

19 nmn 10/3/86


NEVADA NUCLEAR WASTESTORAGE INVESTIGATIONS PROJECT

NRC INTERACTIONS

ISSUES HIERARCHY

0 DOE/HQ (DON ALEXANDER) EXPECTS TO HOLD A MEETING WITH NRC TO DISCUSS THEISSUES HIERARCHY

- GENERIC- DEVELOPMENT OF SITE SPECIFIC INFORMATION NEEDS- STRATEGY/PERFORMANCE ALLOCATION

0 SCHEDULE: LATE OCTOBER

13 DMD 10/2/86


NEVADA NUCLEAR WASTE STORAGEINVESTIGATIONS PROJECT

NRC INTERACTIONS

INDEPENDENCE OF Q-PERSONNEL

10 CFR 50, APPENDIX B, CRITERIA , ORGANIZATION"

THEPERSONS PERFORMING QUALITY ASSURANCE FUNCTIONS SHALL HAVE SUFFICIENTAUTHORITY AND ORGANIZATIONAL FREEDOM TO IDENTIFY QUALITY PROBLEMS; TO INITIATE,RECOMMEND, OR PROVIDE SOLUTIONS; AND TO VERIFY IMPLEMENTATION OF SOLUTIONS.

SUCH PERSONS AND ORGANIZATIONS PERFORMING QUALITY ASSURANCE FUNCTIONS SHALLREPORT TO A MANAGEMENT LEVEL SUCH THAT THIS REQUIRED AUTHORITY ANDORGANIZATIONAL FREEDOM, INCLUDING SUFFICIENT INDEPENDENCE FROM COST ANDSCHEDULE, WHEN OPPOSED TO SAFETY CONSIDERATIONS, ARE PROVIDED.

... THE INDIVIDUAL(S) ASSIGNED THE RESPONSIBILITY FOR ASSURING EFFECTIVEEXECUTION OF ANY PORTION OF THE QUALITY ASSURANCE PROGRAM...SHALL HAVE DIRECTACCESS TO SUCH LEVELS OF MANAGEMENT AS MAY BE NECESSARY TO PERFORM THISFUNCTION.

14 DMD 10/2/86

U .S. DEPARTMENT OF ENERGY

NEVADA NUCLEAR WASTE STORAGE

INVESTIGATIONS PROJECT

NRC INTERACTIONS

MINI-AUDITS

0 NRC AUDITS OF SPECIFIC PROJECT ACTIVITIES- PROVIDE PARTICIPANTS THE EXPERIENCE OF NRC AUDITS

- NRC INTERESTS/ATTITUDES- NRC AUDIT TECHNIQUES- TECHNICAL CONCERNS

- PROVIDE NRC OPPORTUNITY TO APPLY LESSONS LEARNED IN REACTOR REGULATIONTO WASTE MANAGEMENT PROGRAM ON INFORMAL BASIS

0 DOE/HQ REQUESTED LISTING OF PARTICIPANTS ACTIVITIES WHICH COULD BEAUDITED

0 NNWSI LIST DISCUSSED AT RECENT PM MEETING

o GROUND RULES:- INFORMAL - DOE NOT YET AN APPLICANT- CONDUCT UNDER APPENDIX 7

o RISK: NEGATIVE VIEW OF PROJECT BY NRC

o BENEFIT: PARTICIPANTS RECEIVE EARLY INPUT ON INFORMAL BASIS

15 DMD 10/2/86

NNWSI PROJECT

SYSTEMS ENGINEERING STATUS

OCTOBER 2 1986

INTRODUCTION

0 WHY SYSTEMS ENGINEERING?

THE MDS PROGRAM IS COMPLEX AND POSES MANYTECHNICAL AND ADMINISTRATIVE CHALLENGES.

"IT IS DOE POLICY TO USE SYSTEMS ENGINEERING INTHE TECHNICAL MANAGEMENT OF ALL MAJOR SYSTEMACQUISITIONS." - OGR SEMP

"SYSTEMS ENGINEERING WILL BE USED BY OGR TOMANAGE. INTEGRATE, AND DOCUMENT ALL ASPECTS OFTHE TECHNICAL DEVELOPMENT OF THE MDS PROGRAM

- OGR SEMP

NNWSI PROJECT WORK BREAKDOWN STRUCTURE FY 198611 MARCH 1986

1.2.1 SYSTEMS

1.2.1.1.S SYSTEMS MANAGEMENT AND INTEGRATION1.2.1.2 SYSTEMS ENGINEERING

1.2.1.2.1.S SYSTEM DESCRIPTION1.2.1.2.2.S SYSTEM STUDIES1.2.1.2.3.S COST SCHEDULE1.2.1.2.4 SYSTEMS ENGINEERING INTEGRATION

1.2.1.2.4.A LANL1.2.1.2.4.G USGS1.2.1.2.4.L LLNL1.2.1.2.4.S SNL1.2.1.2.4.T SAIC

1.2.1.2.5.T CONFIGURATION MANAGEMENT &CHANGE CONTROL

WBS FY1986 - CONTINUED

1.2.1.3 TECHNICAL DATA BASE MANAGEMENT

1.2.1.3.1.S TUFF DATA BASE1.2.1.3.2.S COMPUTER GRAPHICS1.2.1.3.3.S REFERENCE INFORMATION BASE

1.2.1.4 TOTAL SYSTEMS PERFORMANCE ASSESSMENT

1.2.1.4.1.S FLOW & RN TRANSPORT1.2.1.4.2.S RN SOURCE TERM1.2.1.4.3.S DEVELOPMENT & CERTIFICATION OF

COMPUTER CODES1.2.1.4.4.S RN RELEASES FROM TOTAL SYSTEM

SYSTEMS ENGINEERING INTEGRATION GROUPSEIG

RESPONSIBILTIES & DUTIESo ASSIST SNL IN PREPARING THE PROJECT SEMP

o PROVIDE GUIDELINES FOR DEVELOPMENT ANDMANAGEMENT OF THE PROJECT'S TECHNICALBASELINE- DEFINE TECHNICAL BASELINE- GUIDE THE PREPARATION OF TECHNICAL

BASELINE DOCUMENTS- REVIEW THE TECHNICAL BASELINE DOCUMENTS- RECOMMEND A TECHNICAL BASELINE CHANGE

CONTROL PROCESS- PARTICIPATE IN THE TECHNICAL BASELINE

CONFIGURATION MANAGEMENT PROCESS- SUPPORT THE WMPO- REVIEW AND RECOMMEND DATA FOR ENTRY INTO

THE RIB

SEIG - CONTINUED

o ENSURE INTEGRATION AND DOCUMENTATION OFPROJECT TECHNICAL ACTIVITIES- ENSURE THAT APPROPRIATE SYSTEM STUDIES ARE

PERFORMED TO SUPPORT MS DEVELOPMENT.- IDENTIFY PROJECT TECHNICAL ACTIVITIES THAT

REQUIRE ADDITIONAL INTEGRATION/COORDINATION.- MONITOR COORDINATING GROUP ACTIVITIES- GUIDE THE PREPARATION OF PROCEDURES TO

CONTROL SYSTEM & SUBSYSTEM INTERFACES.- CONDUCT REVIEWS OF DEVELOPING MDS DESIGN.- REVIEW AND RECOMMEND FOR APPROVAL EACH

PARTICIPANT'S PROCEDURES FOR IMPLEMENTING

SEMP REQUIREMENTS.

SEIG MEMBERS

JOHN ROBSON - DOE-VMPO-CHAIRMAN

GARY YEAGER - SNLLEO KLAMERUS - SNLMIKE REVELLI - SNLGARY RYALS - USGSDICK HERBST - LOS ALAMOSDOK DOKUZOGUZ - SAICAD HOC MEMBERS AS APPROPRIATE FROM WMPO ANDOTHER PROJECT PARTICIPANTS

NNWSI PROJECT TECHNICAL BASELINE DOCUMENTS

APPROVAL DEVELOPMENT MAINTENANCEDOCUMENT LEVEL RESPONSIBILITY RESPONSIBILITY

YUCCA MOUNTAIN MINEDGEOLOGIC DISPOSALSYSTEM REQUIREMENTS

YUCCA MOUNTAIN MINEDGEOLOGIC DISPOSALSYSTEM DESCRIPTION

OGR SNL SNL

OGR SNL SNL

NNWSI REFERENCEINFORMATION BASELINE

REPOSITORY SUBSYSTEMDESIGN REQUIREMENTS

DESIGN INTERFACE

PROJECT

OGR

PROJECT

SNL SNL

SNL SNL

SNL SNL

WASTE PACKAGE SUBSYSTEMDESIGN REQUIREMENTS

EXPLORATORY SHAFTFACILITY SUBSYSTEMDESIGN REQUIREMENTS

OGR LLNL LLNL

OGR WMPO WMPO

SYSTEMS ENGINEERING MANAGEMENT PLAN

SEMP

o GENERAL- DIRECTED BY OGR SEMP- APPROVED BY OGR- DEMONSTRATES THE PROJECT'S COMMITMENT TO

UTILIZING SYSTEMS ENGINEERING IN THEDEVELOPMENT OF THE MDS

- PREPARED BY SNL WITH ASSISTANCE FROM SEIG

o STATUS- AUTHOR REVIEW COMMENTS BEING INCORPORATED- SEIG MEMBERS PRESENT DRAFT FOR TPO REVIEW

WEEK OF OCTOBER 6- COPY TO OGR FOR INFORMAL REVIEW- RESOLVE TPO COMMENTS AND REISSUE- SNL INTERNAL REVIEW- WMPO & OGR FORMAL REVIEW

o CONTENTS- FOLLOWS OGR-SEMP FORMAT TO 2ND LEVEL

NNWSI PROJECT

SYSTEMS ENGINEERING MANAGEMENT PLAN (SEMP)

CONTENTS

1.0 INTRODUCTION

1-1 POLICY

1-2 PURPOSE

1-3 DIRECTIVES AND REFERENCES

1-4 ORGANIZATION OF NNWSI PROJECT SEMP

2.0 SCOPE AND APPLICABILITY

3.0 APPROACH

3.1 NNWSI PROJECT SYSTEMS ENGINEERING

PROCESS

3.2 SYSTEMS ENGINEERING INTEGRATION GROUP

(SEIG)

4.0 IMPLEMENTATION

4.1 SYSTEMS ENGINEERING TECHNIQUES

4.2 APPLICATION OF SYSTEMS ENGINEERING

TECHNIQUES TO DEVELOPMENT AND MANAGEMENT

OF TECHNICAL BASELINE

4.3 APPLICATION OF SYSTEMS ENGINEERING

TECHNIQUES TO NNWSI PROJECT TECHNICAL

ACTIVITIES

4.4 INTERFACE OF SYSTEMS ENGINEERING WITH

OTHER PROJECT ACTIVITIES

5.0 DOCUMENTATION

5.1 RESPONSIBILITIES AND AUTHORITY

5.2 SYSTEMS ENGINEERING DOCUMENTATION

5.3 DOCUMENT REVISIONS

6.0 REFERENCES

APPENDIX A - ACRONYMS

APPENDIX - COORDINATING AND WORKING GROUPS

SYSTEMS-ENGINEERING DOCUMENTATION

OGR SYSTEMS-ENGINEERING DOCUMENTATION

OGR PLAN FOR SYSTEMS STUDIESGENERIC REQUIREMENTS FOR A MINED GEOLOGIC

DISPOSAL SYSTEM GR)OGR SYSTEMS STUDY REPORTSOGR REVIEW RECORD MEMORANDA

PROJECT-LEVEL SYSTEMS-ENGINEERING DOCUMENTATION

APPROVAL LEVELPROJECT SYSTEMS ENGINEERINGMANAGEMENT PLAN OGR

SITE-SPECIFIC MGDS DESCRIPTION OGRSITE-SPECIFIC MGDS REQUIREMENTS OGRSITE-SPECIFIC SUBSYSTEM REQUIREMENTS OGRPROJECT SYSTEMS STUDY REPORTS PROJECTDESIGN REPORTS PROJECTPROJECT REVIEW RECORD MEMORANDA PROJECT

REF.: SYSTEMS ENGINEERING MANAGEMENT PLAN FORTHE OFFICE OF GEOLOGIC REPOSITORIES[1985)

ONGOING MAJOR SYSTEMS ENGINEERING ACTIVITIES

o PREPARATION OF SEMP

o TECHNICAL BASELINE DEVELOPMENT- REQUIREMENTS DOCUMENTS- SYSTEM DESCRIPTION- TECHNICAL DATA BASE

o TECHNICAL DATA MANAGEMENT- SITE & ENGINEERING PROPERTIES DATA BASE

(SEPDB)- INTERACTIVE GRAPHICS INFORMATION SYSTEM

(IGIS)- REFERENCE INFORMATION BASE RIB)- INPUT FROM PARTICIPANTS- OUTPUT TO IMS. LSS- ACTIVE IN TDM PLANNING MEETINGS

o SYSTEMS ENGINEERING AS APPLIED TO THE SITECHARACTERIZATION PLAN USING THE ISSUESHIERARCHY, ISSUES RESOLUTION STRATEGY, ANDPERFORMANCE ALLOCATION.

o SEIG TO ASSIST IN CLARIFYING DEFINITION OF TERMSCRITICAL TO THE PROJECT.

TECHNICAL DATABASE STATUSNEVADA NUCLEAR WASTE STORAGE


* ORGANIZING DAT.A AND RECORDS INTO CENTRAL LOCATION(S)

- INTERACTION WITH RECORDS CENTER

- INTERACTION WITH IMS

* ORGANIZING PARTICIPANTS TO PROVIDE FOR DATA FLOW INTODATABASE

- WMPO WORKING GROUP

- SEIG INTERACTION

- PROCEDURE DEVELOPMENT


NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONSPROJECT

TECHNICAL DATABASE STATUS[continued)

. ESTABLISHING AND IMPLEMENTING REFERENCE INFORMATION BASE

- INITIAL DRAFT(COMMENTS)

- SEIG INTERACTION

- MAKING A(DESIGN.

PART OF PRODUCTSPA. CHARACTERIZATION)

REPORTING PROGRESS ON ABOVE

- PARTICIPANT MONTHLY REPORT

- SUMMARY

APPENDIX A

TECHNICAL DATA BASE

A. CANDIDATE IFORMATION FOR SITE AND ENGIEERING PROPERTIES DATA BASE

1. "Fluid Flow in a Fractured Rock-mass (sand85-0855) by E. A.Klavetter and . R. R. Peters.

2.

3.

3. DATA Formally submitted to the site and engineering properties dataBASE

1. Rocl-Mass classication of Candidate Repository Units atYucca Mountain" (Sand62-2034) by B. S. Langkopf amd P. R. Gnirk.

U.S. Department of Energy

NEVADA NUCLEAR WASTE STORAGE


SUBMITTALS TO THE NNWSI CENTRAL DATA BASEr

Period of Record

: TPO : DATE OF SUBMITTAL : DESCRIPTION OF DATA


NEVADA NUCLEAR WASTE STORAGEINVESTIGATIONS PROJECT

TECHNICAL DATA BASE

o RESPONSE TO ACTION ITEM FROM JULY TPO MEETING

- TEAM FORMED TO DEVELOP PROCEDURE TO IMPLEMENT SNL PROPOSED PROJECTTECHNICAL DATA BASE MANAGEMENT SYSTEM

o AT AUGUST TPO MEETING (9/4/86), TPO's AGREED TO APPOINT REPRESENTATIVESTO THE TDB MANAGEMENT SYSTEM PLANNING MEETING

o ON SEPTEMBER 30, 1986, PLANNING MEETING WAS HELD AT SAIC

o ALL PARTICIPANTS, EXCEPT FS, WERE REPRESENTED

DMD 10/2/861



TECHNICAL DATA BASE

RESULTS OF TECHNICAL DATA BASE PLANNING MEETING

- DEFINED THE NEEDED PROJECT LEVEL REQUIREMENTS PROCEDURES

- DEFINED THE PARTICIPANTS' IMPLEMENTING PROCEDURE SCOPES

- IDENTIFIED MAJOR ISSUES/CONCERNS

- ESTIMATED THE RESOURCES NECESSARY TO PREPARE PROCEDURES AND IMPLEMENTTHE SYSTEM

- FORMULATED RECOMMENDATIONS

DMD 10/2/86

SNL TECHNICAL DATA National

BASE DATA CYCLE LboratoriesM

ISSUES HIERARCHY

2. ISSUES RESOLUTION STRATEGY

PERFORMANCE ALLOCATION

4. PARAMETER NEEDS

5.TESTING

6. RAW TEST RESULTS

7. REDUCED DATA & SUPPORING DOCUMENTAION

CENTRAL RECORDS STORAGE



TECHNICAL DATA BASE

PROJECT LEVEL (WMPO) REQUIREMENTS

PROCEDURES NEEDED TO DEFINETECHNICAL DATA BASE SYSTEM

1) REQUIREMENT FOR LOCAL DATA RECORDS STORAGE

2) REQUIREMENTS FOR SCREENING AND IDENTIFICATION OF DATA FOR ENTRY INTO

TECHNICAL DATA BASE

3) REQUIREMENTS FOR CONTROL OF TECHNICAL DATA BASE PRODUCTS

4) REQUIREMENTS FOR THE REFERENCE INFORMATION BASE

DMD 10/2/864

U. S. DEPARTMENT OF ENERGY


TECHNICAL DATA BASE

PARTICIPANTS PROCEDURE SCOPES

1) LOCAL DATA RECORDS STORAGE FACILITY OPERATION

- DATA TURNOVER FROM PRINCIPAL INVESTIGATORS- INDEXING AND STORAGE OF DATA- CONTROL OF DATA- INTERACTION WITH ARMS- -RELEASE OF DATA TO NRC/COMPLIANCE WITH AGREEMENTS

2) DATA SCREENING BY DISCIPLINE-ORIENTED WORKING GROUPS

- CRITERIA FOR DATA SELECTION FOR TDB- INTERACTION WITH DBA- REVIEW/APPROVAL BY TPO

DMD 10/2/865

U. S. DEPARTMENT OF ENERGY


MAJOR ISSUESo RELEASE OF DATA

- COMPLIANCE WITH DOE/NRC PROCEDURAL AGREEMENT

o DATA CATALOG-TIMINGo RESPONSE TO DATA REQUEST-TIMINGo DETAIL LEVEL OF TEST SCHEDULE

- RELEASE OF DATA TO PROJECT PARTICIPANTS FOR PROJECT USES

o PROFESSIONAL ENHANCEMENT vs. PROJECT NEEDS

- STATE/PUBLIC ACCESS TO DATA

o PRINCIPAL INVESTIGATOR/DATA BASE ADMINISTRATOR COMMUNICATION

- P1'S NEED TO COMMUNICATE NEEDS TO DATA BASE ADMINISTRATOR (AND VICEVERSA) TO FACILITATE TRANSFERS OF DATA TO TDB

o FORMATo DEGREE OF DATA REDUCTION

DMD 10/2/866



TECHNICAL DATA BASE

MAJOR ISSUES (CONT)

o NECESSITY TO INCLUDE ENVIRONMENTAL DATA" IN THE PROJECT SYSTEM

- ENVIRONMENTAL- RADIOLOGICAL- SOCIOECONOMIC- ENVIRONMENTAL

DMD 10/2/86



TECHNICAL DATA BASE

ESTIMATED RESOURCES

o PREPARATION PROJECT LEVEL REQUIREMENTS PROCEDURES

FOUR MAJOR PROCEDURES AT 2 MAN-WEEKS EACH

o PREPARATION PARTICIPANTS IMPLEMENTING PROCEDURES

APPROXIMATELY 35 PROCEDURES AT ONE MAN-WEEK EACH

8 MAN WEEKS

35 MAN WEEKS

ABOUT 40-50 MAN WEEKS

o IMPLEMENTATION OF PROCEDURES AT PARTICIPANTS LOCATIONS 15-30 FTE's

DMD 10/2/86A.


NevADANUCLEAR WAST STORAGE INVESTIGATIONS PROJECT

TECHNICAL DATA BASE

APPROACH/RECOMMENDATIONS

o PREPARE PROJECT LEVEL REQUIREMENTS PROCEDURESo PARTICIPANTS REVIEW, CONCURo PARTICIPANTS DEVELOP COST, SCHEDULE TO PREPARE IMPLEMENTING

PROCEDURESo SNL CONTINUE TO PREPARE TECHNICAL DATA BASE GENERAL

REQUIREMENTS (NO ADDITIONAL RESOURCES)o SNL CONTINUE TO DESIGN/INSTALL TB SYSTEM (NO ADDITIONAL RESOURCESRESOURCES

BY 1/15/87BY 2/15/87BY 3/15/87

MARCH TPO4/15/87

o PRESENT PARTICIPANTS COST/SCHEDULE ESTIMATES TO TPO'so APPROVAL TO PROCEED

o PARTICIPANTS PREPARE/OBTAIN WMPO APPROVAL OF PROCEDURES BY 9/1/87

*

o SNL COMPLETE TDB SPECIFIC REQUIREMENTS - DATA BASE PLAN(BASED ON CHAPTER 8.3, SCP)

o SYSTEM IMPLEMENTATION (VAX 7500, VAX 8200, INGRESS)

BY 1/1/87

BY 1/1/87

DMD 10/2/869

NNWSI QA UPDATE

OCTOBER 1-2, 1986 (TPO MEETING)

o STATUS OF STOP WORK ORDER

o NEW REQUIREMENT FROM OGR

o PROJECT-WIDE CONTROLS - IMPLEMENTATION TO MEET QA REQUIREMENTS

o NON-DOE OBSERVERS ON DOE AUDITS

o Q-LIST METHODOLOGY

USGS STOP WORK ORDER STATUS

CONDITIONS TO RESUME WORK:

o PROPOSED CORRECTIVE ACTIONS AND SCHEDULES FOR COMPLETION OF AUDIT FINDINGS APPROVED BY WMPO.

o QAPP REVISED AND APPROVED BY WMPO.

o INDOCTRINATION AND TRAINING COMPLETE.

o PLAN TO PROVIDE ADEQUATE QA COVERAGE.

o ASSIGNMENT OF QA LEVELS COMPLETED AND APPROVED BY WMPO.

STATUS:

o ALL OF THE AUDIT FINDING CORRECTIVE ACTIONS WERE SUBMITTED AND REVIEWED BY WMPO.

- SIXTEEN (16) OF THE TWENTY TWO (22) WERE ACCEPTABLE TO WMPO.

- THE REMAINING SIX (6) WILL BE DISCUSSED DURING A MEETING WITH USGS TO BE HELD IN OCTOBER.

o WMPO HAS REVIEWED AND FOUND ACCEPTABLE 95% OF THE USGS QAPPs. ACCEPTANCE OF THE REMAINING 5% ISANTICIPATED BY OCTOBER 10, 1986.

o NO INDOCTRINATION AND TRAINING ON THE USGS QAPP HAS STARTED (AWAITING WMPO APPROVAL OF THE QAPP).LIMITED TRAINING ON HOW TO PREPARE SIPs WAS INITIATED.

o NO QA RESOURCE PLAN SUBMITTED TO WMPO AS REQUESTED.

o WMPO HAS PROVIDED COMMENTS TO A DRAFT USGS SIP THAT WILL SERVE AS THE PROTOTYPE SIP. NO USGS SIPSUBMITTED FORMALLY. ESTIMATED NUMBER OF SIPs REQUIRING WMPO APPROVAL IS FORTY FIVE (45).

SAIC/LANL/LLNL STOP WORK ORDER STATUS

CONDITION TO RESUME WORK:

o ASSIGNMENT OF QA LEVELS COMPLETE AND APPROVED BY WMPO.

STATUS:

SAIC:

o ALL OF SAIC QALASs HAVE BEEN COMMENTED ON AND RETURNED.

o SAIC HAS PREPARED TWO (2) DRAFT SIPs AND ASSOCIATED QALASs. A REVIEW MEETING WITH WMPO AND SAIC ISEXPECTED TO TAKE PLACE THE WEEK OF OCTOBER 6, 1986. EXPECTED NUMBER OF SIPs REQUIRING WMPOAPPROVAL IS THREE (3).

LOS ALAMOS:

o TEN (10) SIPs AND ASSOCIATED QALASs HAVE BEEN APPROVED BY WMPO ALLOWING WORK TO CONTINUE ON THESEACTIVITIES.

o WMPO HAS RETURNED COMMENTS ON ONE (1) SIP WHICH SHOULD BE RESOLVED BY OCTOBER 10, 1986.

o WMPO IS PRESENTLY REVIEWING THE QA LEVELS ASSIGNED TO ITEMS IN ESF.

o ABOUT THREE (3) SIPs REMAIN TO BE SUBMITTED TO AND REVIEWED BY WMPO.

LLNL:

o TWO (2) DRAFT SIPs HAVE BEEN SUBMITTED TO AND COMMENTED ON BY WMPO DURING A REVIEW MEETING.

o TWO (2) DRAFT SIPs ARE IN PROCESS OF WMPO REVIEW. A REVIEW MEETING WITH LLNL IS SET FOR THE WEEKOF OCTOBER 6, 1986. EXPECTED NUMBER OF SIPs REQUIRING WMPO APPROVAL IS ELEVEN (11).

SNL STOP WORK ORDER STATUS


o WMPO APPROVAL OF THE SNL QAPP

o ASSIGNMENT OF QA LEVELS COMPLETE AND APPROVED BY WMPO

STATUS:

o WMPO HAS REVIEWED AND ACCEPTED 50% OF THE SNL QAPP..

- COMMENTS AND PROPOSED RESOLUTIONS WERE AGREED TO ON 30% OF THE QAPP NOT YET APPROVED.

- 20% OF THE QAPP (SECTION 4, 7, 17, AND 18) REMAINS TO BE SUBMITTED TO WMPO FOR REVIEW ANDAPPROVAL.

o THE MAJORITY OF SNL SIPs AND QALASs HAVE BEEN APPROVED BY WMPO.

THREE (3) REMAIN TO BE SUBMITTED

- SIX (6) WERE COMMENTED ON BY WMPO DURING A REVIEW MEETING WITH SNL

REECO STOP WORK ORDER STATUS

STATUS:

o WMPO APPROVAL OF PROPOSED AUDIT FINDING CORRECTIVE ACTIONS

o WMPO APPROVAL OF THE REECo QAPP

o COMPLETION OF INDOCTRINATION AND TRAINING OF REECo PERSONNEL


o ALL PROPOSED CORRECTIVE ACTIONS HAVE BEEN SUBMITTED AND ALL BUT THREE (3) HAVE BEEN ACCEPTED BYWMPO. INFORMAL AGREEMENT HAS BEEN REACHED ON THE REMAINING THREE (3).

o REECo HAS SUBMITTED A REVISED QAPP. APPROXIMATELY 40% OF IT WAS ACCEPTABLE TO WMPO. COMMENTS WERERETURNED TO REECo FOR RESOLUTION.

o NO INDOCTRINATION OR TRAINING ON THE REECo QAPP HAS STARTED.

ANTICIPATED REMOVAL OF STOP WORK ORDER

PROBLEM:

o CONFLICT WITH WMPO TECHNICAL REVIEWERS DUE TO ENVOLVEMENT ON SCP PIRCs.

IMPACT: COMMENT/REVIEW MEETINGS WITH THE PARTICIPANTS ARE BEING DELAYED.

ASSUMPTION:

o PARTICIPANTS WILL HAVE THE NECESSARY IMPLEMENTING PROCEDURES IN PLACE TO PERFORM THE WORK.

USGS: FEBRUARY/MARCH 1987

LOS ALAMOS: ALREADY LIFTED ON ACTIVITIES THAT HAVE AN APPROVED SIP AND QALASNOVEMBER 1986

SAIC: DECEMBER 1986

LLNL: NOVEMBER 1986

SNL: NOVEMBER 1986

REECo: DECEMBER 1986

NEW REQUIREMENTS FROM OGR

o ADVANCE NOTICE TO OGR WHEN NRC PARTICIPATES IN PROJECT AUDITS

o OGR TECHNICAL REVIEW OF TECHNICAL PLANS, STATUS AND PROGRESS REPORTS, SCIENTIFIC/TECHNICAL REPORTS SUBMITTEDBY THE PROJECT (UNCLEAR AS TO WHAT SPECIFIC DOCUMENTS WILL REQUIRE SUCH REVIEW AND IF APPROVAL ISNECESSARY).

o OGR WILL PARTICIPATE IN PROJECT READINESS REVIEWS DURING SITE CHARACTERIZATION TESTING. CONSTRUCTION ANDOPERATION. OGR TO REVIEW READINESS REVIEW PLANS AND REPORTS.

o MANAGEMENT ASSESSMENT PROCESS OF QA PROGRAM SPECIFIED IN DETAIL.

- EFFECTIVENESS OF SYSTEM OF MANAGEMENT CONTROLS ESTABLISHED TO ACHIEVE QUALITY

- ADEQUACY OF QA RESOURCES

- VERIFY QA PROGRAM IMPLEMENTATION

- PERSONNEL ARE TRAINED TO QA REQUIREMENTS

- METHOD OF ANALYSIS, REPORTING AND TRACKING OF RESULTS

- METHOD OF TRACKING RECOMMENDATIONS

o PROJECT OFFICE SUBMITTAL TO OGR OF THE CHECKLIST USED TO EVALUATE COMPLIANCE OF PROJECT QA PLAN WITH THE NRCQA REVIEW PLAN.

o POSITION DESCRIPTION DEVELOPMENT FOR PERSONNEL PERFORMING QA LEVEL I & II ACTIVITIES

- QUALIFICATION OF PERSONNEL BASED ON POSITION DESCRIPTION

- IDENTIFICATION OF CAPABILITIES

NEW REQUIREMENTS FROM OGR(CONTINUED)

o INDOCTRINATION PROGRAM TO INCLUDE THE FOLLOWING AS A MINIMUM

- QA PLANS AND PROCEDURES

- TECHNICAL PROCEDURES AND WORK INSTRUCTIONS

- REGULATIONS

- PROGRAMMATIC DOCUMENTS

o USE OF CHECKLIST TO REVIEW PARTICIPANT QA PROGRAMS

o NEED TO DEVELOP A PROCEDURE FOR DETERMINING A "Q" LIST

o DOCUMENTATION OF REQUIREMENTS OF EXPERIMENT AND RESEARCH.

o EXPANSION OF PEER REVIEW REQUIREMENTS

o QA REQUIREMENTS FOR EACH QA LEVEL (SEE ATTACHED)

o REQUIREMENTS FOR RELIABILITY (ACCEPTANCE) OF DATA

- SAME AS SOP-02-03 EXCEPT,

- INCLUDES LEVEL 2 DATA

PROJECT-WIDE CONTROLS WHICH NEED TO BE DEVELOPED TO MEET QA REQUIREMENTS

o SYSTEMS ENGINEERING MANAGEMENT PROCESS AND NNWSI ADMINISTRATIVE PROCEDURE (AP) TO CONTROL

- DESIGN INTERFACE

- SITE INVESTIGATION INTERFACE

o CONFIGURATION MANAGEMENT PROCESS AND NNWSI APs TO IMPLEMENT

- DISSEMINATION OF PROJECT-WIDE DOCUMENTS, INFORMATION AND POSITIONS

o PROJECT DATA BASE AND NNWSI APs TO IMPLEMENT (TUFF, RIB, GRAPHICS)

- INPUT OF DATA

- DISSEMINATION OF DATA

- INTERFACE WITH QARMS/IMS IF ANY

o SAMPLE FACILITY PROCESS AND APs TO CONTROL

- HANDLING OF SAMPLES

- SHIPPING OF SAMPLES

- STORAGE OF SAMPLES

- IDENTIFICATION OF SAMPLES

o READINESS REVIEW SYSTEM

o NNWSI/OGR INTERFACE PROCEDURE TO CONTROL

- OGR REVIEW OF PROJECT TECHNICAL DOCUMENTS

- OGR REVIEW OF QA DOCUMENTS

OGR QA SUPPLEMENT NO. 12 (DRAFT) PROTOCAL FOR OBSERVING DOE QA AUDITS

o DURING PRE-LICENSING ACTIVITIES

o LIMITS ONE (1) OBSERVER TO AN AUDIT

o OBSERVER TRAINED, QUALIFIED AND CERTIFIED AS AN AUDITOR

o AUDIT PLAN, CHECKLIST, QA PLANS, SENT TO OBSERVER

o LIMITS OBSERVER PARTICIPATION

- ATTEND AND PARTICIPATE IN AUDIT TEAM CAUCUS, PRIOR TO AND DURING AUDIT

- ATTEND PRE AND POST AUDIT MEETING WITH AUDITED ORGANIZATION

- DIRECT QUESTION, COMMENTS, AND CONCERNS TO COGNIZANT AUDIT TEAM MEMBER

o REQUIRES OBSERVER TO PREPARE A REPORT WITH SIMILAR CONTENT AS AN AUDIT REPORT, FOR INCORPORATION IN THEFINAL AUDIT REPORT BY THE AUDIT TEAM LEADER.

o INITIAL WMPO CONCERNS

- SUPPLEMENT NO. 12 SHOULD BE A C&C AGREEMENT

- INTENT/PURPOSE OF THE OBSERVER IS UNCLEAR

- PERFORM AN INDIVIDUAL AUDIT- CRITIQUE HOW DOE PERFORMS AN AUDIT

- CONSIDER LEAD AUDITOR QUALIFICATIONS AS A MINIMUM FOR OBSERVER

- CONFLICTS BETWEEN DOE LEAD AUDITOR AND OBSERVER

Q-LIST PREPARATION PROCESS

o OGR QA SUPPLEMENT NO 3 ISSUED

o REQUIRES PROJECT TO DEVELOP A PROCEDURE FOR DETERMINING ITEMS AND ACTIVITIES TO BE PLACED ON THE PROJECTQ-LIST

o REFERENCES OGR DOCUMENT "METHODOLOGY FOR FORMULATING A Q-LIST AT THE SCP DESIGN STAGE. THE Q-LIST IS TOINCLUDE THE "STRUCTURES, SYSTEMS, COMPONENTS

- AND ACTIVITIES ESSENTIAL TO THE PREVENTION OR MITIGATION OF ANY SENARIO WITH A PROBABILITY OFOCCURRENCE OF 1 X 10 OR GREATER AND DOSE CONSEQUENCES EXCEEDING 500 MREM."

- AND SITE CHARACTERIZATION ACTIVITIES THAT ARE ESSENTIAL TO ADEQUATELY EVALUATE THESE ITEMS, WILL BEBASED ON TECHNIAL JUDGMENT OF THE ITEMS THAT WILL BE FOUND NECESSARY TO COMPLY OR DEMONSTRATECOMPLIANCE WITH THE REPOSITORY PERFORMANCE OBJECTIVES AS THE REPOSITORY PERFORMANCE ANALYSES ARECOMPLETED."

o IMPLIES THE USE OF A CONSERVATIVE APPROACH.


REGULATORY DEFINITIONSPRESENTED TO

PM-TPO MEETING

PRESENTED BY

DON VIETH

October 1, 1986

Nevada Operations OfficeUNITED STATES DEPARTMENT OF ENERGY


NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECTBASIS

DEFINITIONFOR INTEREST IN

OF REGULATORY TERMS

* TECHNICAL LEADERSHIP

BURDEN OF PROOF RESTS WITH THEAPPLICANT

* TERMS MUST BE DEFINED WITH TWO POINTSIN MND:

- INTERNAL CONSISTENCY

- STRUCTURED SUCH THAT THEY PROMOTE SOLUTIONSTO PROBLEMS RATHER THAN DISCOURAGE SOLUTIONS



CLASSES OF DEFINITIONS

* BOUNDARIES

ABILITY TO DRAW A LINE ON A MAP OR A FIGURE

* CONCEPT

ABILITY TO ESTABLISH A MEANINGFUL DESCRIPTION,PHYSICAL SIGNIFICANCE, AND/OR QUANTATIVEMEASURE OF AN ABSTRACT IDEA



Q � � � � � � � � � � �

FOUR DEFINITIONS

2

3

ANTICIPATED PROCESSES AND EVENTS

UNANTICIPATED PROCESSES AND EVENTS

ENGINEERED BARRIER SYSTEM

SUBSTANTIAL COMPLETE CONTAINMENT4.



ANTICIPATED /PROCESSES

UNANTICIPATEDAND EVENTS

* ANTICIPATED PROCESSES AND EVENTS

MEANS THOSE NATURAL PROCESSES AND EVENTS THAT EXIST OR OCCUR INDIVIDUALLY,OR IN COMBINATION WITHIN THE GEOLOGIC SETTING THAT HAVE A CUMULATIVEPROBABILITY OF OCCURRING WHICH IS EQUAL TO, OR GREATER THAN, 0.1 DURINGTHE PERIOD AFTER PERMANENT CLOSURE THAT THE INTENDED PERFORMANCE OBJECTIVEMUST BE ACHIEVED. INADVERTENT INTRUSION IS SPECIFICALLY EXCLUDED FROMTHIS CATEGORY.

* UNANTICIPATED PROCESSES AND EVENTS

MEANS THOSE NATURAL PROCESSES AND EVENTS INDIVIDUALLY, OR IN COMBINATIONAFFECTING THE GEOLOGIC SETTING THAT HAVE A CUMULATIVE PROBABILITY OFOCCURRING WHICH IS LESS THAN 0.1, BUT EQUAL TO OR GREATER THAN, 0.0001AND THOSE PROCESSES AND EVENTS INADVERTENTLY INITIATED BY HUMAN ACTIVITIESDURING THE PERIOD THAT THE INTENDED PERFORMANCE OBJECTIVES MUST BE ACHIEVED.



ENGINEERED BARRIER SYSTEM

* ENGINEERED BARRIER SYSTEMINCLUDES THE WASTE PACKAGE AND THE UNDERGROUND FACILITY.NB: THE EDGE OF THE UNDERGROUND FACILITY WILL IDENTIFY THE BOUNDARY OFTHE ENGINEERED BARRIER SYSTEM. THE DEFINITION OF THE UNDERGROUND FACILITYIS THE SAME AS INVOLVED IN 10 CFR 60.

U.S.DEPARTMENT OF ENERGY


SUBSTANTIALLYCOMPLETE CONTAINMENT

* SUBSTANTIALLY COMPLETE CONTAINMENT

IS ACHIEVED, CONSIDERING POST-CLOSURE ANTICIPATED PROCESSES AND EVENTS, ASLONG AS THE TOTAL QUANTITY OF ANY SPECIFIC RADIOISOTOPE RELEASED FROM ALLOF THE EMPLACED WASTE PACKAGES OVER THE TIME INTERVAL FROM REPOSITORYCLOSURE TO ANY TIME AT WHICH THE MEASUREMENT OF THE DEGREE OF CONTAINMENTIS MADE DOES NOT EXCEED THE TOTAL QUANTITY OF THAT RADIOISOTOPE ALLOWED TOBE RELEASED FROM THE ENGINEERED BARRIER SYSTEM DURING AN EQUIVALENT TIMEINTERVAL AFTER THE END OF CONTAINMENT; HOWEVER, THIS CONDITION DOES NOTAPPLY TO RADIOISOTOPES WITH RADIOACTIVE DECAY HALF-LIVES OF LESS THAN 45YEARS


NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECTEXAMPLES OF TERMSNEEDING GOOD DEFINITIONS

OR BASIS FOR SPECIFYING TERMS

* ANTICIPATED PROCESSES AND EVENTS* UNANTICIPATED PROCESSES AND EVENTS* SUBSTANTIALLY COMPLETE CONTAINMENT* ENGINEERED BARRIER SYSTEM* UNDERGROUND FACILITY* DISTURBED ZONE* SITE* RESTRICTED AREA* CONTROLLED AREA* ACCESSIBLE ENVIRONMENT

DRAFT LIST OF INVESTIGATIONS DISTRIBUTED AT SCP MEETING ON 8/27-28/86

BWIP

BASALT WASTE ISOLATION PROJECT

SITE CHARACTERIZATION PLAN INVESTIGATIONS

August 86

Page of 4

SCP SECTION 8.3INVESTIGATIONS

8.3.1.2 Geology

Stratigraphic and Structural Model DevelopmentMineralogic and Petrologic CharacterizationTectonic Events and Processes

8.3.1.3 Hydrology

Surface Water InvestigationGround Water Investigation

8.3.1.4 Geochemistry

Hydrochemical Characterization InvestigationRadionuclide Reactivity Investigation

8.3.1.5 Climatology

Paleoclimate Characterization StudyFuture Climate Study

8.3.1.6 Resource Potential

Mineral Resource PotentialWater Resource Potential

of 4

SCP SECTION 8.3 INVESTIGATIONS

8.3.2.2 Verification of Measurement of Host Rock Environment

Pre-excavation Host Rock EnvironmentPost-subsurface Excavation Host Rock EnvironmentPost-Waste Emplacement Host Rock Environment

8.3.2.3 Coupled Interaction Tests

Two-fold InteractionsThree-fold InteractionsFour-fold Interactions

8.3.2.4 Design Optimization

Surface SubsystemUnderground Facility Access ShaftsUnderground Facility SubsystemSubsurface Personnel and Materials Transport SubsystemSubsurface Ventilation and Air Conditioning SubsystemSubsurface Support SubsystemMine Water Control SubsystemSurface / Subsurface Common SubsystemBulk Materials Handling and Processing SubsystyemWaste Handling SubsystemSubsurface Closure Subsystem

8.3.2.5 Repository Modeling

Constitutive ModelingRepository Geomechanics AnalysesAdditional Repository Design Models

8.3.2.6 Waste Retrieval

Waste EmplacementWaste Retrieval

8.3.2.7 Radiological Health and Safety of Workers

Normal Operational Radiological Protection/Dose QuantificationPerformance Verification Systems

8.3.2.8 Non-radiological Health and Safety of Workers

Surface Facility Health and SafetyUnderground Facility Health and Safety

of 4

SCP SECTION .3 INVESTIGATIONS

8.3.3.2 Seals Subsystem EnvironmentCompilation

of Site and Engineered Barriers Subsystem Datacharaterization of damaged rock zone.

8.3.3. Seals Subsystem Component and Interactions Testing

Laboratory Testing for Seals Materials Properties/InteractionField Testing for Seals Materials Properties and

Demonstration of Emplacement MethodsIn Situ Testing for Verification of Seals Properties

and Emplacement Methods

8.3.3.4 Seals Subsystem Design Optimization

Selection of Seals Materials, Configurations and LocationsDevelopment of Installation Procedures

8.3.3.5 Seals Subsystem Modelling

Allocation of Performance and Confidence GoalsSensitivity StudiesPerformance Assessments

of 4

SCP SECTION 8.3 INVESTIGATIONS

8.3.4.2 Waste Package Environment

Post-Emplacement Environment CharacterizationNatural Analogs and Artifacts

8.3.4.3 Waste Package Components and Interaction Testing

Waste FormsContainer Materials TestingPacking Materials TestingWaste Package Radionuclide Behavior

5.3.4.4 Waste Package Design Development

Design ActivitiesContainer DevelopmentPacking DevelopmentQualification Testing

8.3.4.5 Waste Package Modeling

Performance SensitivityPerformance and ReliabilityPreclosure SafetyModel Validation

LIST OF "INVESTIGATIONS" PROVIDED BY NNWSI PROJECT AT SCP MEETINGON 8/27-28/87.THIS LIST IS EQUAL TO THE INFORMATION NEED IN THECURRENT ISSUES HIERARCHY, EXCEPT THAT "COMPILATION-TYPE" INFO NEEDSWERE DELETED. 8/26/86

SCP INFORMATION NEED NUMBERSAND INVESTIGATION (INFORMATION NEED) TITLES

SITE PROGRAM

GEOHYDROLOGY (Postclosure)

1.13.1 Description of the regional hydrologic system.

1.13.2 Description of the unsaturated zone hydrologic system at the site.

1.13.3 Description of the saturated zone hydrologic system at the site.

HYDROLOGY (Preclosure)

4.8.1 Flood recurrence intervals and levels at potential locations ofsurface facilities.

4.8.2 Location of adequate water supplies.

4.8.3 Ground water conditions within and above the potential host rock.

GEOCHEMISTRY (Postclosure)

1.14.1 Water chemistry within the potential emplacement horizon and alongpotential flow paths.

1.14.2 Mineralogy, petrology, and rock chemistry within the potentialemplacement horizon and along potential flow paths.

1.14.3 Stability of minerals and glasses at the site.

1.14.4 Radionuclide retardation by sorption processes along flow paths tothe accessible environment.

1.14.5 Radionuclide retardation by precipitation processes along flow pathsto the accessible environment.

1.14.6 Radionuclide retardation by dispersive/diffusive/advective transportprocesses along flow paths to the accessible environment.

1.14.7 Radionuclide retardation by all processes along flow paths to theaccessible environment.

1.14.8 Retardation of gaseous radionuclides along flow paths to theaccessible environment.

ROCK CHARACTERISTICS (Postclosure)

1.15.1 Stratigraphy and structure necessary to locate the undergroundfacility.

1.15.2 Spatial distribution of thermal and mechanical properties.

1.15.3 Spatial distribution of ambient stress conditions and ambient thermalconditions.

ROCK CHARACTERISTICS (Preclosure)

4.7.1 Stratigraphic and structural information necessary to define theboundaries of the underground facility.

4.7.2 Spatial distribution of thermal and mechanical properties.

4.7.3 Spatial distribution of ambient stress and thermal conditions.

CLIMATIC CONDITIONS (Postclosure)

1.16.1 Nature and rates of change in climatic conditions to predict futureclimates.

1.16.2 Potential effects of future climatic conditions on hydrologiccharacteristics.

1.16.3 Potential effects of future climatic conditions on geochemicalcharacteristics.

1.16.4 Potential effects of future climatic conditions on rockcharacteristics.

EROSION (Postclosure)

1.17.1 Present locations and rates of surface erosion.

1.17.2 Potential effects of future climatic conditions on locations andrates of erosion.

1.17.3 Potential effects of tectonic activity on locations and rates oferosion.

1.17.4 Potential effects of erosion on hydrologic characteristics.

1.17.5 Potential effects of erosion on geochemical characteristics.

1.17.6 Potential effects of erosion on rock characteristics.

ROCK DISSOLUTION (Postclosure)

1.18.1 Rates of dissolution of crystalline and non-crystalline components intuff.

TECTONICS (Postclosure)

1.19.1 Rates and magnitudes of potential igneous activity.

1.19.2 Nature and rates of tectonic processes, ncluding faulting, folding,uplift and subsidence, and seismic activity.

1.19.3 Potential effects of igneous and tectonic activity and hydrologiccharacteristics.

1.19.4 Potential effects of igneous and tectonic activity on geochemicalcharacteristics.

1.19.5 Potential effects of igneous and tectonic activity on rockcharacteristics.

TECTONICS (Preclosure)

4.9.1 Rates and magnitudes of potential igneous activity that could have animpact at the site.

4.9.2 Potential fault movements at the site.

4.9.3 Ground motion at the site from potential man-made or natural seismicevents.

SURFACE CHARACTERISTICS (Preclosure)

4.6.1 Topographic characteristics of potential locations of surfacefacilities.

4.6.2 Soil and bedrock properties of. potential locations of surfacefacilities.

4.6.3 Local meteorological conditions at potential locations of surfacefacilities.

HUMAN INTERFERENCE (Postclosure)

1.20.1 Natural phenomena and human activities that might degrade surfacemarkers and monuments.

1.20.2 Present and future value of energy, mineral, land, and ground waterresources.

1.20.3 Potential effects of exploiting natural resources on hydrologic,geochemical and rock characteristics.

WASTE PACKAGE PROGRAM

WASTE PACKAGE (Postclosure)

1.10.2 Reference waste package designs.

1.10.3 Reference waste package emplacement configuration.

1.10.4 Description of the post-emplacement near-field environment of thewaste packages, including the expected range of environmentalcharacteristics under conditions appropriate for the referenceemplacement configuration.

WASTE PACKAGE (Preclosure)

2.6.3 Waste acceptance specifications.

WASTE PACKAGE PRODUCTION TECHNOLOGY (Preclosure)

4.3.1 Identification and evaluation of production technologies forfabrication, closure, and inspection of the waste package.

REPOSITORY PROGRAM

UNDERGROUND FACILITY CONFIGURATION (Postclosure)

1.11.3 Design concepts for orientation, geometry, layout, and depth of theunderground facility that contribute to waste containment andisolation including flexibility to accommodate site-specificconditions.

1.11.4 Design constraints to limit water usage and potential chemicalchanges.

1.11.5 Design constraints to limit excavation-induced changes to rockmasspermeability.

1.11.6 Predicted thermal and thermomechanical response of the host rock,surrounding strata, and ground-water system.

1.11.7 Reference postclosure underground facility designs.

REPOSITORY DESIGN CRITERIA (Preclosure)

2.7.3 Identification and description of safety-related items, radiationzones, and normal and accident conditions, including disruptiveevents.

2.7.4 Means to limit worker internal and external radiation exposures,including ventilation, time, distance, and shielding.

2.7.5 Means to monitor and control radiation exposure conditions, includingmeans to respond to emergencies.

2.7.6 Means to assure nuclear criticality safety.

2.7.7 Means to manage onsite generated radioactive waste and todecommission surface facilities.

2.7.8 Means of complying with mining regulations to ensure radiologicalsafety.

TECHNICAL FEASIBILITY

4.4.3 Plan for repository operations during construction, operation,closure and decommissioning.

4.4.4 Repository design requirements for construction, operation, closure,and decommissioning.

4.4.5 Reference preclosure repository design.

4.4.6 Development and demonstration or required equipment.

4.4.7 Design analyses, including those addressing impacts of surfaceconditions, rock characteristics, hydrology, and tectonic activity.

4.4.8 Identification of technologies for surface facility construction,operation, closure, and decommissioning.

4.4.9 Identification of technologies for underground facility construction,operation, closure, and decommissioning.

4.4.10 Identification of technologies for emplacement of seals for accesses,drifts, and boreholes.

SEAL SYSTEM PROGRAM

SHAFT AND BOREHOLE SEALS CHARACTERISTICS

1.12.2 Materials and characteristics for seals for shafts, drifts, andboreholes.

1.12.3 Placement methods for seals for shafts, drifts, and boreholes.

1.12.4 Reference design of seals for shafts, drifts and boreholes.

PERFORMANCE ASSESSMENT PROGRAM

WASTE RETRIEVABILITY

2.1.2 Determination that access to the waste emplacement boreholes can beprovided throughout the retrievability period for normal andoff-normal conditions.

2.1.3 Determination that access to waste containers can be providedthroughout the retrievability period for normal and off-normalconditions.

2.1.4 Determination that the waste can be removed from the emplacementboreholes for normal and off-normal conditions.

2.1.5 Determination that the waste can be transported to the surface anddelivered to the waste handling surface facilities for normal andoff-normal conditions.

2.1.6 Determination that the retrieval requirements set forth in 10 CFR60.111 (b) are met using reasonably available technology, as requiredby 10 CFR Part 960.

RADIOLOGICAL SAFETY

2.3.1 Determination of radiation environment in surface and subsurfacefacilities due to natural radioactivity.

HLF - PRECLOSURE RADIOLOGICAL SAFETY

2.5.1 Determination that the site is not disqualified and is not likely tobe disqualified for each of the disqualifying conditions.

2.5.2 Determination that the site meets the qualifying conditions of thetechnical guidelines and is likely to continue to meet the qualifyingconditions.

2.5.3 Determination that the site meets the qualifying condition of thesystem guideline and is likely to continue to meet the qualifyingcondition.

HLF- EASE/COST CONSTR., OPER., CLOS., AND DECOMM.



4.1.3 Determination that the site meets the qualifying conditions of thesystem guideline and is likely to continue to meet the qualifyingcondition.

WASTE PACKAGE CONTAINMENT

1.4.1 Waste package design features that affect the performance of thecontainment barrier.

1.4.2 Material properties of the containment barrier.

1.4.3 Scenarios and models needed to predict the time to loss ofcontainment and the ensuing degradation of the containment barrier.

1.4.4 Estimates of the rates and mechanisms of containment barrierdegradation in the repository environment for anticipated andunanticipated processes and events.

1.4.5 Determination of the time to loss of substantially completecontainment of the waste packages for anticipated processes andevents.

EBS CONTAINMENT

1.5.1 Waste package design features that affect the rate of radionucliderelease.

1.5.2 Material properties of the waste forms.

1.5.3 Scenarios and models needed to predict the rate of radionucliderelease from the waste package and engineered barrier system.

1.5.4 Determination of the release rates of radionuclides from theengineered barrier system for anticipated and unanticipated processesand events.

1.5.5 Determination of the amount of the radionuclides leaving thenear-field environment of the waste package.

PRE-WASTE-EMPLACEMENT GWTT

1.6.2 Calculational models to predict ground-water travel times in theunsaturated and saturated zones.

1.6.3 Identification of the paths of likely radionuclide travel from thedisturbed zone to the accessible environment, and identification ofthe fastest path.

1.6.4 Determination of the pre-waste-emplacement ground-water travel timealong the fastest path of likely radionuclide travel from thedisturbed zone to the accessible environment.

1.6.5 Boundary of the disturbed zone.

POSTCLOSURE SYSTEM PERFORMANCE

1.1.2 Design concepts for the repository system that may reduce or delaythe releases of radionuclides to the accessible environment.

1.1.3 A set of most-probable release scenarios that address bothanticipated and unanticipated conditions.

1.1.4 Calculational models to predict radionuclide releases to theaccessible environment.

1.1.5 Determination of the radionuclide releases to the accessibleenvironment associated with the most-probable scenarios.

1.1.6 Probabilistic estimates of the radionuclide releases to theaccessible environment considering anticipated and unanticipatedscenarios.

PROTECTION OF GROUND-WATER

1.3.1 Determination that no special sources of groundwater exist at YuccaMountain.

SITE EVALUATION (AGAINST SITING CRITERIA)

1.8.1 Site information needed to identify favorable and potentially adverseconditions at the site that may influence postclosure repositoryperformance.

1.8.2 Identification of favorable and potentially adverse conditions at thesite that may influence postclosure repository performance.

1.8.3 Potential effects of potentially adverse conditions on postclosurerepository performance.

1.8.4 Determination that the performance objectives relating to isolationof the waste can be met considering the presence of favorable andpotentially adverse conditions identified in Information Need 1.8.2

HLF - POSTCLOSURE SYS. AND TECH. SITING GUIDELINES



1.9.3 Determination that the site meets the qualifying condition of thesystem guideline and is likely to continue to meet the qualifyingconditions.

1.9.4 Calculations for cumulative releases to the accessible environmentduring 100,000 years as required by 10 CFR 960.3-1-5.

REDUNDANCY IN STUDY PLANHANDOUT E9/3/86

Pg 1/6

-Metal Barrier Testing-Waste Package Performance Analysis

-Metal Barrier Testing-Waste Package Performance Analysis

-Class Waste Form Testing-Spent Fuel Testing

-Glass Waste Form Testing-Spent Fuel Testing

-Glass Waste Form Testing-Spent Fuel Testing-Waste Package Performance Analysis-Geochemical Modeling

-Geochemical Modellng-Glass Waste Form Testing-Spent Fuel Testing-Waste Package Performance Analysis

-Geocheomical Modeling-Glass Waste Form Testing-Spent Fuel Testing-Integrated Testing-Waste Package Performance Analysis

-Geochemical Modeling-Integrated Testing-Waste Package Performance Analysis




-Gochemical Modeling-Integrated Testing-Waste Package Performance Analysis



-Waste Package Design



2.2.3.22.2.5

2.2.3.2

-Laboratory Hydrologic Measurements

-Seal Materials Development Plan

-Hydrologic Mechanism Investigation







-Laboratory Hydrologic Measurements

-Laboratory Hydrologic Measurments

-Laboratory Hydrologic Measurements-Hydrologic Mechanism Investigation

-Laboratory Hydrologic Measurements-In Situ Thermomechanical Investigations

-Excavation Investigations

-Excavation Investigations

-Laboratory Hydrologic Measurements-Hydrologic Mechanism Investigation-In Situ Thermomechonical Investigations





1.2.4.2.1.4

1.2.4.2.3.2

1.2.4.2.3.2

1.2.4.2.3.2

-In Situ Mechanical Properties-In Situ thermomechanical Investigations-Laboratory Thermal Properties-Laboratory Thermal Expansion Testing-Laboratory Mechanical Properties of Intact Rock-Laboratory Mechanical Properties of Fractures

-Excavation Investigations-In Situ Mechanical Properties-In Situ thermomechanical Investigations

seismotectonic field Studies for Repository Surface Facilities

-Seismotectonic Field Studies for Repository Surface

-Excavation Investigations-In Situ Mechanical Properties-In Situ Thermomechanical Investigations-Excavation Investigations


-Selsmotectonic Field Studies for Repository Surface




-Excavation Investigations-In Situ Mechanical Properties-In Situ Thermomechanical Investigations-Seismotectonic Field Studies for Repository Surface-Laboratory Thermal Properties-Laboratory Thermal Expansion Testing-Laboratory Mechanical Properties of Intact Rock-Laboratory Mechanical Properties of Fractures

-Excavation Investigations-In Situ Mechanical Properties-In Situ thermomechanical Investigations-Seismotectonic Field Studies for Repository Surface


Seismotectonic Field Studies for Repository Surface Facilities



-Selemotectonic Field Studies for Repository Surface

Facilities

Facilities

Facilities

facilities

facilities

facilities

facilities

facilities

facilities

facilities

facilities

facilities

facilities

pg 5/6

USGS

8.3.1.3.1 3 -Characterization of the Regional Surface Water-Caracterization of the Regional Groundwater Flow System-Regional Hydrologic System Synthesis and Modeling

8.3.1.3.2 -Quaternary Unsaturated Zone Hydrochemical Analysis-Characterization of Unsaturated Zone Infiltration-Characterization of Percolation In the Unsaturated Zone-Chartztionof Flux w/in the Paintbrsh Nonwided Unit near Ghost Dnce Ft-Hydrochemical Characterization of the Unsaturated Zone-Characterization of Gaseous-Phase Movement In the Unsaturated Zone-Unsaturated Zone System Analysis and Integration-Matrix Hydrologic Properties Laboratory Analysis-Intact-Fracture Test in the Exploratory Shaft Facility-Water-Flow and chemicalt Thru Frctre etwks In Variably Saturatd

Welded Tuff in the Exploratory Shaft Facility-Bulk-Permeability Test in the Exploratory Shaft Facility-Radial-Borehole Tests in the Exploratory Shaft Facility-Excavation-Effects Test in ther Exploratory Shaft Facility-Calico Hills Test nthe Exploratory Shaft Facility-Perched-Water Test in the Exploratory Shaft Facility

-Characterization of the Site Saturated Zone Groundwater Flow System-Saturated Zone Hydrologic System Synthesis and Modeling

characterization of the vert and lat Distrib of stratigraphic units w/in Site-Characterization of Site Structural features-Exploratory Shaft Facility Geologic studies

-Characterization of the Present Regional Climate and Environments-Regional Paleolimnologic Studies-Regional Teffestrial Paleoecologic Studies-Synthesis of the Paleonvironmental History of the Yuc Mtn Region-Characterization of the Future Regional Climate and Environments

-Analysis of Future Surface Hydrology due to Climate Changes-Chrzt'n of the Future Regional Hydrology due to climate Changes-Characterization of the Quaternary Regional Hydrology

-Distribution and Characteristics of Present-Day Erosion-Distribution and Characteristics of Past Erosion

-Investigation of Wrench Faulting Along Geologic Province Boundary-Investigation of Left-Lat Strike-Slip Faulting on NE-Trending Systems-Investigation of Detachment Faults in and Adjacent to NTS-Investigation of Normal and Strike-Slip Faulting on N-Trending Systems-Investigation of Rifting (Death Valley-Pancake Range Zone)-Investigation of folds in Miocene and Younger Rocks of Region-Tectonic Geomorphology of NTS and Vicinity-Investigation of Regional Stress Field and its Bearing on the

Orientation and Style of Future Fault Movement-Geodetic Leveling (Regional Uplift and Subsidence)-Regional Studies of Seismicity-Characterization of Regional Lateral Crustal Movement

-Chrzt n of the Future Regional Hyd due to Future Igeous Tect Actv ty-Characterization of the Future Unsaturated Zone Hydrology due to

Future Igneous and Tectonic Activity

1.2.3.3.11.2.3.3.3.4

-Characterization of the Site Ambient Thermal Conditions-Characterizations of the Site Ambient Stress Conditions

-Regional Paleoflood Evaluation-Site Flood and Debris-Hazards Studies

1.2.3.2.2.41.2.6.9.2.1

Redundancy in information need

STUDY PLAN

9/3/86page 1 of 7

lABORATORY THERMAL EXPANSION TESTING

METAL BARRIER TESTING

SORPTION AS A FUNCTION

OF CONCENTRATION

OF SORBING ELEMENT

GW COMP

AND ATMOSPHERE

of 7

USGS

1.15.1 Characterization of Vertical Lateral Distributionof Stratigraphic Units w/in the Site Area

Characterization of Site Structural Features

Geophysical and Rock Properties Testing

Chrzt'n of the Site Ambient Thermal Conditions

lnvstgt'n of Wrench Faulting Along Geologic Province Boundary

Invstgt'n of Left-Lateral Strike-Slip Faulting on NE-Trending Systems

Invstgt'n of Detachment Faults in and Adjacent to NTS

Investigation of Normal and Strike-Slip Faulting on NE-Trending Systems

investigation of Rifting

Invstgt n of Folds In Miocene and Younger Rocks of Region

Tectonic Geomorphology of NTS and Vicinity

Distrib and Characteristics of Present Day Erosion

Distrib and Characteristics of Past Erosion

Investigation of Regional Stress Field and its Bearing on theOrientation and Style of Future Fault Movement

Geodetic Leveling

Regional Studies of Seismicity

Regional Studies of Seismicity

Characterization of Regional Lateral Crustal Movement

Characterization of the Regional Surface Water

REGIONAL PALEOFLOOD EVALUATIONRegional Paleoflood Evaluation

Analysis of Future Surface Hydrology due to Climate Changes

Site Flood and Debris-Hazards Studies

Characterization of the Site Saturated Zone GW Flow System

Saturated Zone Hydrologic System Synthesis and Modeling

| Characterization of the Regional GW FLow System

Regional Hydrologic System Synthesis and Modeling

Characterization of the Future Regional Hydrology due toFuture Igneous and Tectonic Activitly

Quaternary Unsaturated Zone Hydrochemical Analysis

Characterization of the Future Regional Hydrology due to Climate Changes

| Characterization of the Future Unsaturated Zone Hydrology due toFuture Igneous and Tectonic Activity

Characterization Unsaturated Zone Infiltration

Characterization of Percolation in the Unsaturated Zone

Characterization of Flux within the Paintbrush Nonwelded Unit in theVicinity of the Ghost Dance Fault

Hydrochemical Characterization of the Unsaturated Zone

Characterization of Gaseous-Phase Movement in the Unsaturated Zone

Unsaturated Zone System Analysis and Integration

Characterization of the Present Regional Climate and Environments

Regional Paleolimnologic Studies

Regional Terrestrial Paleoecologic Studies

Synthesis of the Paleoenvironmental History of the Yucca Mnt Region

page 6 of 7

1.13.2

of 7

Perched-Water Test In the Exploratory Shaft Facility

0 1

Number of Study Plans per Participant

Organization # of unique Study Plans

Study Plans listed by section number 9/3/86

Sect. # of Study Plans assigned to sections

SNL LANL LLNL USGS

8.3.1 28 25 1 51

* Some study plans are associated with more than one section of 8.3

Number Study Plans Associated with Issue Types 9/3/86

Organization Performance Design Characterization

*Some study plans are associated with more than one issue or issue type.

DRAFT LIST OF STUDY PLANS DISTRIBUTED AT SCP MEETING ON 8/27-28/86BWI P

BASALT WASTE ISOLATION PROJECT

SITE CHARACTERIZATION STUDY PLANS

(Tabulated with reference to higher level investigations)

August 1986

BWIP SCP Section 8.3 INVESTIGATIONS/STUDY PLANS

8.3.1.2 GEOLOGYStratigraphic and Structural Model Development

* Stratigraphy* Structural Geology* Intraflow Structure* Cooling Joint Characteristics

Mineralogic and Petrologic Characterization* Mineralogic and Petrologic Characterization

Tectonic Events and Processes* Structural Geology* Deformation* Seismology* Tectonic Model Development

8.3.1.3 HYDROLOGYSurface Water Investigation* Surface Water System* Site Flooding

Ground Water Investigation* Regional Groundwater System* Site Groundwater

8.3.1.4 GEOCHEMISTRYHydrochemistry* Groundwater Flow System Hydrochemistry* Groundwater Redox

Radionuclide Retardation* Radionuclide Reactivity

8.3.1.5 CLIMATOLOGYPaleoclimate* Paleoclimate

Future Climate* Future Climate

8.3.1.6 RESOURCE POTENTIALMineral Resource Potential* Mineral, Hydrocarbon, and Geothermal Resource Potential

Water Resource Potential* Water Resource Potential

8.3.2.2 VERIFICATION OF MEASUREMENT OF HOST ROCK ENVIRONMENTPre-Excavation Host Rock Environment* Stress State in Host Rock* Thermal Properties of Host Rock* Mechanical Properties of Host Rock

Post-Subsurface Excavation Host Rock Environment* Stress State in Host Rock* Opening Performance/Stability

Post-Waste Emplacement Host Rock Environment* Stress State in Host Rock* Opening Performance/ Stability

8.3.2.3 COUPLED INTERACTION TESTSTwo-Fold Interactions in Repository Program* Stress State in Host Rock* Hydromechanical (HM) Interactions

Three-Fold Interactions In Repository Program* Thermomechanical-Chemical (TMC) Interactions* Thermohydromechanical (THM) Interactions

Four-Fold Interactions In Repository Program* Thermohydromechanical-Chemical (THMC) Interactions

8.3.2.4 DESIGN OPTIMIZATIONSurface Subsystem* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Underground Facility Access Shafts* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Underground Facility Subsystem* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Subsurface Personnel and Materials Transport Subsystem* Advanced Conceptual/ License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Subsurface Ventilation and Air Conditioning Subsystem* Advanced Conceptual/License Application Designs* Site Characterzation Data Needs* Constructibility Data Needs

Subsurface Support Subsystem* Advanced Conceptua/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Mine Water Control Subsystem* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Surface/Subsurface Common SubsystemAdvanced Conceptual/License Application Designs

* Site Characterization Data Needs* Constructibility Data Needs

Bulk Materials Handling and Processing Subsystem* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Waste Handling Subsystem* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Subsurface Closure Subsystem* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

8.3.2.5 REPOSITORY MODELINGConstitutive Modeling* Constitutive Model Development* Constitutive Model Validation

Repository Geomechanics Analyses* Shaft Analyses* Shaft Pillar/Service Opening Analyses* Emplacement Room Analyses* Emplacement Borehole Analyses* Intersection Analyses

Additional Repository Design Models* Surface Facilities and Equipment Design Analyses* Underground Facilities and Equipment Design Analyses

8.3.2.6 WASTE RETRIEVALWaste Emplacement* Advanced Conceptual/License Application Designs* SCP-CDR Emplacement Systems

Waste Retrieval* Retrievability Strategy Report* Retrieval Environment and Retrieval Scenarios* Retrieval Equipment Development and Demonstration* Retrieval Accident Analyses

8.3.2.7 RADIOLOGICAL HEALTH AND SAFETY OF WORKERSNormal Operation Radiological Protection/Dose Quantification* Advanced conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

Provision of Performance Verification Systems* Advanced Conceptual/License Application Designs* Site Characterization Data Needs* Constructibility Data Needs

8.3.2.8 NONRADIOLGICAL HEALTH AND SAFETY OF WORKERSSurface Facility Health and Safety* OSHA Requirements* MSHA Requirements

Underground Facility Health and Safety* MSHA Requirements

8.3.3.3 SEALS SUBSYSTEM COMPONENT AND INTERACTIONS TESTINGLaboratory Testing for Seals Materials Properties and Interactions* Optimization of Reference Seals Materials* Effects of Elevated Temperatures on Physical Properties of

Reference Seals Materials* Long Term Stability of Seals Materials* Characterization of Reference Seals Materials* Interface Properties of Reference Seals Materials

Field Testing for Seals Materials Properties and Demonstration ofEmplacement Methods

* Demonstration of Subsurface Borehole Seals Installation* Demonstration of Drift Seals Installation

in Situ Testing for Verification of Seals Properties andEmplacement Methods

* Demonstration of Subsurface Borehole Seals Performance* Demonstration of Surface Borehole Seals Installation and

Performance* Demonstration of Drift Seals Performance* Demonstration of Shaft Seals Installation and Performance* Characterization of the Damaged Rock Zone Sealing* Characterization of Emplaced Shaft Liner Grout

8.3.3.4 SEALS SUBSYSTEM DESIGN OPTIMIZATIONSelection of Seals Materials Configurations and Locations* Selection of Seals Materials, Configurations, and Locations

Development of Installation Procedures* Development of Installation Procedures for Seals

8.3.3.5 SEALS SUBSYSTEM MODELINGAllocation of Performance and Confidence Goals* Allocation of Performance and Confidence Goals to Seals

Subsystem Components

Sensitivity Studies* Sensitivity Studies of Seals Subsystem Performance

Performance Assessments* Determination of Compliance with Seals Subsystem Performance

Goals for Expected Repository Conditions* Determination of Compliance with Seals Subsystem Performance

Goals for Scenario Conditions

8.3.4.2 WASTE PACKAGE ENVIRONMENTPost-Emplacement Environment Characterization* Waste Package Environment:Basalt/Groundwater Interactions* Waste Package Environment:Geochemical Environment

Natural Analogs and Artifacts* Waste Package Natural Analogs* Waste Package Metallic Artifacts

8.3.4.3 WASTE PACKAGE COMPONENTS AND INTERACTION TESTINGWaste Forms* Waste Form Information* Waste Form Test Materials* Waste Form/Filler Materials Interactions* Waste Acceptance Specifications

Container Materials Testing* Container Testing:General Corrosion* Container Testing:Pitting Corrosion* Container Testing:Crevice Corrosion* Container Testng:Environmentally Assisted Cracking

Packing Materials Testing* Packing Materials Testing:Chemical Stability* Packing Materials Testing:Physical Properties and Processes

Waste Package Radionuclide Behavior* Radionuclide Solubility/Sorption and Speciation Behavior* Waste/Barrier/Rock Interactions:Spent Fuel Release Testing* Waste/Barrier/Rock Interactions:Borosilicate Glass ReleaseTesting

* Waste/Barrier/Rock Interactions:Other Waste Forms

8.3.4.4 WASTE PACKAGE DESIGN DEVELOPMENTDesign Activities* Trade Studies* Design Studies* Container Design and Construction Standard

Container Development* Pressure Vessel Container Development* Monolith Container Development* Container Handling and Safety Testing

Packing Development* Packing Fabrication* Packing Nondestructive Examination* Packing Handling and Emplacement

Qualification Testing* Container Corrosion Qualification Test* Packing Saturation Qualification Test* Container Settlement Test* Waste Package In-Situ Test

8.3.4.5 WASTE PACKAGE MODELINGPerformance Sensitivity* Thermal Transport* Resaturation* Container Lifetime* Radionuclide Release and Transport* Radiation Shielding* Structural Strength

Performance and Reliablity* Thermal Transport* Resaturation* Container Lifetime* Radionuclide Release and Transport* Radiation Shielding* Criticality* Structural Strength* Failure Mode and Effects

Preclosure Safely* Container Fracture

Model Validation* Thermal Transport* Packing Saturation* Container Lifetime* Radionuclide Release and Transport* Radiation Shielding* Criticality* Stress

DRAFT LIST OF STUDY PLANS DISTRIBUTED AT SCP MEETING ON 8/27-28/86

NNWSI PROJECT

8/26/86

STUDY PLANS

LOS ALAMOS

1. Saturated Zone Ground Water Studies (no methods, tech procedures)

2. Three Dimensional Mineral Distributions at Yucca Mountain

3. History of Mineralogic and Geochemical Alteration at Yucca Mountain

4. Smectite, Zeolite, and Glass Dehydration and Transformation

5. Kinetic and Thermodynamic Studies of Mineral Reactions

6. Batch Sorption Studies

7. Sorption as a Function of Concentration of Sorbing Elements, Ground WaterComposition, and Atmosphere

8. Sorption on Particulates and Colloids

9. Statistical Analysis of Sorption Data and Model Development

10. Dissolved Species Concentration Limits

11. Colloid Behavior

12. Crushed Tuff Column Experiments

13. Mass Transfer Kinetics

14. Unsaturated Tuff Columns

15. Fractured Tuff Column Studies

16. Diffusion

17. Filtration

18. Integrated Transport Calculations

19. Analysis of Physical/Chemical Processes Affecting Transport

20. Computer Models and Related Support

21. Gaseous Radionuclide Transport Calculations

22. Gaseous Radionuclide Transport Measurements.

23. Water Movement Tracer Tests

24. Volcanism Drill Holes

25. Revised Probability Calculations

LLNL

1. Geochemical Modeling

2. Integrated Testing

3. Waste Package Performance Analysis

4. Metal Barrier Testing

5. Other Materials Testing

6. Waste Package Design

7. Glass Waste Form Testing

8. Spent Fuel Testing

9. Exploratory Shaft Waste Package Environment Test

10. Waste Package Environment

SNL

1. Laboratory Hydrologic Measurements

2. Hydrologic Mechanism Investigations

3. Seal Materials Development Plan

4. Excavation Investigations

5. In Situ Mechanical Properties

6. In Situ Thermomechanical Properties

7. Laboratory Thermal Properties

8. Laboratory Thermal Expansion Testing

9. Laboratory Mechanical Properties of Intact Rock

10. Laboratory Mechanical Properties of Fractures

11. Seismotectonic Field Studies for Repository Surface Facilities

USGS

1. Gravity Surveys

2. Magnetic Surveys

3. Remote Sensing Studies

4. Magneto-Telluric Surveys

5. Characterization of the Regional Surface Water

6. Characterization of the Regional Groundwater Flow System

7. Regional Hydrologic System Synthesis and Modeling

8. Isotope Geology Dating

9. Quaternary Unsaturated Zone Hydrochemical Analysis

10. Characterization of Unsaturated Zone Infiltration

11. Characterization of Percolation in the Unsaturated Zone

12. Characterization of Flux w/in the Paintbrush Nonwelded Unit near the GhostDance Fault

13. Hydrochemical Characterization of the Unsaturated Zone

14. Characterization of Gaseous-Phase Movement in the Unsaturated Zone

15. Unsaturated Zone System Analysis and Integration

16. Matrix Hydrologic Properties Laboratory Analysis

17. Intact-Fracture Test in the Exploratory Shaft Facility

18. Water-Flow and Chemical Transport Through Fracture Networks in VariablySaturated Welded Tuff in the Exploratory Shaft Facility

19. Bulk-Permeability Test in the Exploratory Shaft Facility

20. Radial-Borehole Tests in the Exploratory Shaft Facility

21. Excavation-Effects Test in the Exploratory Shaft Facility

22. Calico Hills Test in the Exploratory Shaft Facility

23. Perched-Water Test in the Exploratory Shaft Facility

24. Characterization of the Site Saturated Zone Groundwater Flow System

25. Saturated Zone Hydrologic System Synthesis and Modeling

26. Characterization of the Site Saturated Zone Groundwater Flow System

27. Development of Fracture Network Model

28. Characterization of the Vertical and Lateral Distribution of StratigraphicUnits w/in Site

29. Characterization of Site Structural Features

30. Development of a Three-Dimensional Model of the Site Geology

31. Exploratory Shaft Facility Geologic Studies

32. Characterization to the Present Regional Climate and Environments

33. Regional Paleolimnologic Studies

34. Regional Terrestrial Paleoecologic Studies

35. Synthesis of the Paleoenvironmental History of the Yucca Mountain Region

36. Characterization of the Future Regional Hydrology due to Climate Changes

37. Analysis of Future Surface Hydrology due to Climate Changes


39. Characterization of the Quarternary Regional Hydrology


41. Distribution and Characteristics of Present-Day Erosion

42. Distribution and Characteristics of Past Erosion

43. Evaluation of Impact of Future Climate Conditions on Location and Rates ofErosion

44. Evaluation of Impact of Future Uplift/Subsidence and Faulting on Erosion atYucca Mountain and Vicinity

45. Evaluation of Impact of Future Erosion on Hydrologic Characteristics atYucca Mountain and Vicinity

46. Seismic Refraction Surveys

47. Seismic Reflection Surveys

48. Investigations of Wrench Faulting Along Geologic Province Boundary

49. Investigations of Left-Lateral Strike-Slip Faulting on Northeast-TrendingSystems

50. Investigation of Detachment Faults in and Adjacent to NTS

51. Investigation of Normal and Strike-Slip Faulting on North-Trending Systems

52. Investigation of Rifting (Death Valley-Pancake Range Zone)

53. Investigation of Folds in Miocene and Younger Rocks of Region

54. Tectonic Geomorphology of NTS and Vicinity (Regional Uplift and Subsidence)

55. Tectonic Model Synthesis

56. Investigation of Regional Stress Field and its Bearing on the Orientationand Style of Future Fault Movement

57. Geodetic Leveling (Regional Uplift and Subsidence)

58. Regional Studies of Seismicity

59. Characterization of Regional Lateral Crustal Movement

60. Characterization of the Future Regional Hydrology due to Future Igneous andTectonic Activity

61. Characterization of the Future Unsaturated Zone Hydrology due to FutureIgneous and Tectonic Activity

62. Characterization of the Site Ambient Thermal Conditions

63. Characterization of the Site Ambient Stress Conditions

64. Site Flood and Debris-Hazards Studies

8.3 LEVEL OF DETAIL FOR PLANS 8/27-28/86

SAMPLE PROVIDED BY HQ/WESTON TO ADDRESS APPROPRIATE LEVEL OF DETAIL FOR SCP

8.3.1.3.4 Information Need 1.14.4

Radionuclide retardation by sorption processes along flow paths to theaccessible environment.

8.3.1.3.4.1 Technical basis for addressing the information need

Link to data chapters

This information need has been referenced in the following sections ofPart A of the SCP: 4.1.3.3.1, 4.1.3.3.2, 4.1.3.3.3, 4.1.3.3.4, 4.1.3.3.5,4.1.3.3.6, 4.1.3.3.7, 4.1.3.6.1

Laboratory and Field Data, Analyses and Model Development Needs

Laboratory data to be gathered in this information need:

Sorption coefficients as a function of: ground-water composition,mineralogy, sorbing species (including oxidation state), waste elementconcentration, temperature, atmosphere,

Sorption kineticsColloidal materialMicrobial activity

Data analyses:Statistical analyses to evaluate critical variables and data gaps

Model development:Model for sorptive behavior (based on lab. experimental data)

Data supplied from other information needs:

Flow paths, fluxes, and velocities of water in the unsaturated zones(1.13.2)Flow paths, fluxes, and velocities of water in the saturated zone (1.13.3)Ground-water composition (1.14.1)Mineralogy, petrology (1.14.2)Stability of minerals and glasses (1.14.3)Potential effects of future climate conditions (1.16.2, 1.16.3, 1.16.4)

Logic

The purpose of this information need is to supply some of the input datafor calculations of radionuclide retardation along potential transportpathways from the repository to the accessible environment at the YuccaMountain site. These calculations are required to address the overall systemperformance objective for radionuclide releases in 10 CFR Part 60 (60.112),and in making findings on the post-closure system guideline and the technicalguideline for geochemistry in the DOE siting guidelines (10 CFR Part 960).

Because numerous variables can effect sorption, the potentially enormousamount of laboratory testing must be limited by the technical approachdeveloped to bound the experiment matrix. The technical approach is to use

DRAFT SCP 123 -1- 9:53 am 08/26/86

laboratory batch and column tests to study the variables singly, and fromthese data, develop the capability to predict sorptive behavior based on theexpected ground water and rock compositions along the flow paths. Theradionuclides of primary concern are identified in Chapter 4 (Sec. 4.1.3.1.1)as the key radionuclides, based on waste inventories and projected chemicalbehavior in the site system. This list is further narrowed by considering thelevel of uncertainty of their behavior, based on existing data, and theirchemistry in the expected environment. More specifically, the actinides arethe main focus of laboratory experiments, due to the complexity of theiraqueous chemistry, sorptive behavior and waste inventories. Of lesserimportance are the radionuclides expected to be in poorly sorbable anionicform, such as , and well understood radionuclides such as cesium andstrontium isotopes. Performance allocation (see sec. 8.3.5. ) has boundedthe test matrix by specifying the Calico ills tuff as the major sorptivebarrier, with the Topopah Springs and the saturated zone rocks to be used asback up support if needed in the system performance calculations. Tests willuse samples of this, and mineralogically equivalent tuffs as well as pureminerals, so that sorptive behavior can be predicted as a function of rockcomposition. Further bounding is done by considering the variations inground-water composition and radionuclide concentrations expected. The rateof release of radionuclides from the spent fuel may also bound the sorptiontesting needed. Radionuclides concentrated along grain boundaries in thespent fuel may be released more rapidly than those in the matrix. The datafrom waste form dissolution experiments should further focus the sorptiontesting program.

Preliminary testing will also define future testing needs, morespecifically radionuclides showing high sorption coefficients (much higherthan needed for the performance assessments) in initial testing do not need tobe the subject of extensive subsequent testing. In this way, scoping testingwill reduce the matrix of testing down to a smaller number of radionuclides.Details of the scoping studies, procedures and laboratory techniques as wellas detailed scheduling, will be contained in the study plans (ref. to studyplans) accompanying the SCP.

The strategy for using sorption data to resolve the characterizationissue (1.14), and the related performance issues (1.1, 1.8 and 1.9), isdescribed in section 8.3.5.8.1. Retardations (R) of greater than 10 and100 have been set as preliminary goals for sorbing and non-sorbing species,respectively. Sorption is one contributor to the total retardation of sorbingspecies. Laboratory data on sorptive behavior is to be collected as anapproximation of expected behavior in the site system. Uncertainty/sensitivity analyses accompanying the performance assessments will define theaccuracy and precision needed in the laboratory data, to establish confidencein the final system analyses.

As described in Chapter 4, sorption behavior is a function of thephysical and chemical variables listed above. In addition, the effects ofmicrobial activity, as well as colloidal and particulate material, onradionuclide sorption and transport are largely unknown at present. Toquantify the sorption behavior, laboratory sorption coefficients will bemeasured by batch and column techniques as a function of the variables listedabove. The effects of microbial activity on radionuclide sorption, as well asthe sorptive behavior of particulate and colloidal material, will also besimulated in laboratory testing.

DRAFT SCP 123 9:53 am 08/26/86

The aim of laboratory testing is to predict sorptive behavior in therock/ground-water system along the potential flow paths to the accessibleenvironment, as a function of radionuclide concentration and speciation underthe important physical/chemical conditions. In this way, a model of thesorptive behavior can be developed, combined with information on ground-watercomposition and flow and rock composition, to produce predictions of overallsystem performance as a function of flow rates and sorption, as well as otherretardation processes.

For laboratory data to be defensible, they must be shown to bereproducible and statistically significant. Standardized procedures have beendeveloped for these types of laboratory testing and will be further developedas needed. The data will be analyzed statistically to develop correlationswith sorptive mineralogy and other important variables affecting sorption. Inaddition to standardized testing, interlaboratory comparison of results isplanned with the NRC.

A final technical consideration that must be addressed to use laboratorydata in retardation calculations is the correlation between laboratory dataand behavior in the field. This correlation can be established with acombination of field testing and natural analog studies. Currently there areplans for field tests for sorbing tracers in the "C" well testing (see Sec.8.3.1.2.3) only, however testing may indicate the need for other field andanalog studies. Based on results of laboratory testing and performanceassessments, critical radionuclides and sorption data may be identified andany additional confirmatory field and analog studies defined.

8.3.1.3.4.2 Planned Studies

Three studies are designed to satisfy this information need, one togenerate laboratory sorption data as functions of the important variablesdiscussed in chapter 4, the second to establish the defensibility of the datastatistically, and the third to generate a predictive model for sorption inthe site system. These studies are planned to be concurrent and interactive,in that data generated will be statistically analyzed to direct future work inconcert with the needs of model development. The studies and subordinatedactivities are listed below. More detailed description of the testingactivities is given in study plans &

Studies1.14.4.1 Laboratory Sorption Testing - Batch Techniques

Activities1.14.4.1.1 Batch tests - solid phase composition1.14.4.1.2 Batch tests - isotherms (sorbing element concentration)1.14.4.1.3 Batch tests - ground water composition1.14.4.1.4 Batch tests - atmosphere1.14.4.1.5 Batch tests - sorption on particulates and colloids1.14.4.1.6 Batch tests - sorption by bacteria

1.14.4.4.2 Statistical Analysis of Experimental Data

1.14.4.2.1 Sorption correlation with mineralogy1.14.4.2.2 Comparison of batch and column tests

DRAFT SCP 123 -3- 9:53 am 08/26/86

1.14.4.3 Sorption Model Development

Study 1.14.4.1 Laboratory sorption testing - batch techniques

The objectives of the laboratory sorption measurements are to supply thedata base for development of a predictive model of sorption processes (study1.14.4.3) and test the preliminary performance allocation for the Calico Hillstuff. This model and the data are then used to support performance assessmentcalculations of radionuclide retardation (reports R537, R572, etc.) done instudies 1.14.7.1-3. Batch tests will be used and compared with column tests(crushed tuff) results done under IN 1.14.6. Results of initial scoping testswill direct further testing to satisfy model development and performanceassessment needs. Radionuclides showing sorption coefficients well in excessof the total retardation (R) goals can be deleted from further testing andthe testing matrix reduced. Modified batch techniques will be used to studyparticulate and colloid sorption behavior, and microbial sorption. Thestatistical analyses and model development studies are conducted in parallelwith the laboratory testing work so that there can be extensive interactionbetween these three efforts. Detailed descriptions of the testing are givenin study plan

Activity 1.14.4.1.1 Batch sorption measurements as a function of solid phasecomposition.

This activity will focus primarily on determining sorption coefficientsfor actinide on tuffs of the Calico Hills zeolitic and vitric units, and onpure minerals representative of the sorptive minerals in those rocks. Thesetests will provide a portion of the data base used to model sorption behavioras a function of the variables discussed above.

Testing inputs and products

Data gathered - sorption coefficients as a function of solid substratecomposition

Data needed - mineral composition of tuff samples from the Calico Hills andother tuffs of similar composition used in the tests

chemical composition of the pure minerals used

grain size, surface area and cation exchange capacity of thesolids used

ground water from well J-13

radioactive tracers* (Pu, Np, Am, U Zr, Ni, Cs, Sr, Ba)

*Procedures for preparing solutions of redox sensitive actinides in knownoxidation states must be developed for the testing. The approach todeveloping these tracers is described in the study plan.

DRAFT SCP 123 -4- 9:53 am 08/26/86

Description of the activity

The test matrix will focus primarily on Pu, Np, Am, U because of theirpresence as key radionuclides and their complex aqueous chemistry. Zr and Niwill also be studied because of their importance in spent fuel inventories.Cs, Sr, and a will be used to test procedures and fill any existing datagaps, since their behavior is well characterized by existing data. Tuffs fromthe Calico ills zeolitic and vitric units will be the focus of the activity.Other tuffs of similar mineralogic composition will be used to supplement thelimited availability of Calico Hills material. Some measurements will also bedone using Topopah Springs tuff and tuffs from the saturated zone since theserocks are considered as barriers held in reserve. Sorption will also bemeasured on pure minerals of composition ranges bracketing those in the YuccaMountain rocks. Clinoptilolite, mordenite and smectite will be the primaryfocus, with some additional testing using calcite. Both sorption anddesorption ratios will be measured, using standardized techniques.Approximately tests are anticipated for this activity. Additiona: testingmay be required based on the analyses of the data and performance assessmentcalculations.

Standardized batch sorption techniques as described in the Los AlamosQuality Assurance Manual (TWS-CNS-DP-05, R: Sorption, Desorption RatioDeterminations of Geologic Materials by a Batch Method) and in Daniels et al.(1982) will be used. Other applicable technical procedures includeTWS-INC-DP-02, R3: Quality Control in Counting Radioactive Nuclides;TWS-MSTQA-QP-15, RO: NNWSI Measurement Control (DRAFT). Nonactinideradioactive tracers will be obtained from standard sources.

Activity 1.14.4.3 Sorption coefficients as a function of ground watercomposition

The objective of this activity is to measure sorption coefficients as afunction of ground water compositions anticipated along potential travelpaths. Ground water composition can control the waste radionuclide oxidationstate, speciation and solubility, and therefore, can have a great effect onthe measured sorption ratio. These data will contribute to the sorption database and support the sorption model development and performance assessmentcalculations. Batch techniques and procedures will be used as described inactivity 1.14.4.1.1.


Data gathered: sorption coefficients as a function of ground-watercomposition.

Data needed: same parameters as in 1.14.4.1.1ground water compositions and samples from wells at YuccaMountainartificially prepared ground waterscomposition of unsaturated zone ground water


Samples of ground water from wells J-13, H-3 and UE 25p-l will be used inthese tests, along with artificially prepared ground water (aw) made by

DRAFT SCP 123 -5- 9:53 am 08/26/86

spiking -13 water with salts to give compositions simulating vadose watercomposition. The actinides U, Pu, Np and Am will be tested primarily withsome testing for Zr, Ni, Cs, Sr, etc. as required to fill gaps in the existingdata base. Batch techniques and procedures will be used as described inactivity 1.14.4.1.1. A general test matrix is given below. More elaborationis provided in the study plan. Approximately tests are anticipated. Thisnumber will be adjusted based on examination of the initial testing results.

element liquid phase solid phase T C atm conc.

[entries are for illustration purposes only]

Activity 1.14.4.1.2 Sorption coefficients as a function of the sorbingelement concentration (isotherms)

The objective of this activity is to develop isotherms for theradionuclides tested. These isotherm data will be used, as part of thesorption data base, to determine at what element concentration levelsprecipitation begins to contribute to the measured sorption ratio; and inmodelling sorption (IN 1.14.7) to predict retardation along flow paths. Sincethe concentration of waste elements is expected to change along potential flowpaths, accurate sorption predictions must account for these changes, iftesting shows the isotherms have significant slopes. Batch techniques andprocedures will be used as described in activity 1.14.4.1.1.


Data gathered: sorption coefficients as a function of sorbing elementconcentration

Data needed: same as activity 1.14.4.1.1


The concentrations studied will try to reach an apparent concentrationlimit, i.e., the highest concentration the solution can maintain when allother variables are held constant, so that it can be shown that precipitationis not contributing to the sorption ratio. The waste elements to be studiedinclude U Pu, Np, Am, Zr, Ni, . from concentrations ranging from lOE-12Mto an apparent concentration limit, if possible. Calico Hills tuff will beused (zeolitic C, and vitric ) along with pure clinoptilolite (cl)mordenite (mor.) and smectite . Test procedures are as for activity1.14.4.1.1. A general test matrix is given below. More elaboration isprovided in the study plan. Approximately _ tests are anticipated. Thisnumber will be adjusted based on initial testing results.

DRAFT SCP 123 -6- 9:53 am 08/26/86

(entries for illustration purposes only]

Activity 1.14.4.1.4 Sorption coefficients as a function of atmosphere

The objective of this activity is to generate sorption coefficients undercontrolled atmospheres intended to maintain the solution pH near 7. In

laboratory atmosphere experiments, the solution pH gradually rises toapproximately 8-8.5, presumably due to loss, whereas Yucca Mountainground waters are closer to pH 7. Data from these tests will be comparedagainst laboratory atmosphere determinations to determine which radionuclidesshow more conservative (lower sorption coefficients) results under thecontrolled C atmosphere more representative of field conditions. Theseconservative data will then become part of the data base supporting modeldevelopment and performance assessments.


Data gathered: sorption coefficients measured under atmospheres

Data needed: same as for activity 1.14.4.1.1


Batch techniques as given for activity 1.14.4.1.1 will be used.Procedure TWS-INC-DP-30, RO, "Partial Atmospheric Control of GroundwaterChemistry," will be used. A general test matrix is given below. Moreelaboration is provided in the study plan. Approximately tests areanticipated. This number will be adjusted based on initial testing results.

element

(entries are for illustration purposes only]

Activity 1.14.1.5 Sorption on particulates and colloids

The objective of this activity is to determine if sorption of importantradionuclides occurs on particulates or colloids that may be present in groundwaters along potential transport pathways. This is an interactive effort with

DRAFT SCP 123 -7- 9:53 am 08/26/86

others described under IN 1.14.5&6, Dynamic Transport. Batch techniques,modified to accommodate the much smaller sample sizes, will be used to measuresorption. If any sorption is measured, then the use of sorption coefficientsalone will not accurately predict the transport of sorbed radionuclides andadditional experiments using column techniques (IN 1.14.6) will be needed tosupply the data for modelling transport. Data generated in this activity willbe part of the sorption data base and used to support performance assessmentcalculations.

Test inputs and products

Data gathered: sorption coefficients on particulatesData needed Particulates from Yucca Mountain

identification of particulate compositionsize distribution of particulatesestimate of size limit for transportable particulates (IN1.14.6)


This activity involves two efforts, (1) collection of particulate andcolloid material and its identification and (2) sorption measurements on theparticulates. Particulate (and colloid) material will be obtained byfiltering ground waters pumped from wells , & around the site.This material will be identified by X-ray diffraction and scanning electronmicroscope analyses. Because of very limited sample availability, batchtesting over the range of radionuclide concentrations and oxidation states,ground-water compositions and other variables measured in previously describedbatch studies, may not be practical. Based on analyses of results from otherbatch tests, the values of these variables showing the most conservativesorption, but still consistent with site conditions, can be selected to set upa smaller test matrix for the particulate tests. Transport calculations canalso be used to limit the number of radionuclides used in the testing to asmaller number than used in other activities. The particulate/colloidsorption tests will not be initiated until preliminary testing and analysis iscompleted for activities 1.14.4.1-4 to allow definition of the test matrix.More elaboration on this activity is given in the study plan.

Activity 1.14.4.1.6 Sorption on Microbes

The objective of this activity is to determine the effects of bacteria onsorption. Tests will be carried out on tuffs in the presence of microbes, onmicrobes alone, on tuffs in the presence of microbial by-products, and in thepresence of microbes and drilling fluid. The nuclide of primary concern isplutonium. As with particulate and colloidal material, if bacteria have aninfluence on sorptive behavior the use of sorption coefficients, measuredwithout their influence, for transport calculations would be suspect. Batchtechniques and procedures will be used as described for activity 1.14.4.1.1,modified to accommodate the sterility requirements of working with microbes.Data generated will be included in the sorption data base and used to supporttransport calculations.

DRAFT SCP 123 -8- 9:53 am 08/26/86

Test inputs and products

Data gathered: Aerobic growth properties of Yucca Mountain microbesAnaerobic growth properties of sameSorption coefficients on tuff samples in the presence ofmicrobesSorption coefficients on microbes themselvesSorption coefficients in the presence of microbialby-productsSorption coefficients in the presence of microbes anddrilling fluids

Data needed: Same parameters as 1.14.4.1.1Microbes isolated from Yucca MountainDrilling fluids used at Yucca Mountain


This activity consists of two efforts, (1) isolation of microbes from thesite and (2) measurements of their effects on sorption behavior. Beforesorption testing can be done, bacteria must be isolated and cultured in thelaboratory. To isolate the bacteria, samples are taken from soils that havereceived discharges of drilling fluids during the course of the drillingoperations and are, therefore, considered likely to contain microorganismscapable of biodegrading drilling fluids. The samples are placed in sterilebottles and immediately returned to the laboratory for analysis. A mineralsalts medium is used to culture these microorganisms. A controlled amount ofdrilling fluid is added as the only energy source for microoorganism growth.Solid media are inoculated with washings of the soil samples. After aerobicor anaerobic incubation at room temperature, isolated bacterial coloniesgrowing vigorously on the medium are transferred to fresh media and incubatedto obtain pure colonies. Colony morphology and microscopic characteristicscan then be determined. This work is covered by QA work plan TWS-INC-WP-18,RO, Microbial Degradation of Drilling Fluids.

The isolated microorganisms can then be used for batch sorption tests.Sorption testing will be done primarily with plutonium, Calico Hills tuff(zeolitic and vitric) and J-13 water under atmosphere. Additionaltesting with other actinides and solid/liquid phase variations will beconsidered based on the results of the testing with plutonium. Additionalelaboration on these tests is given in the study plan.

[This illustrative example includes only the laboratory testing study. Thestatistical analyses and model development studies are not included i thisexample.]

8.3.1.3.4.3 Where this information will be used

The information provided by the above studies for addressing thisinformation need will be used in considering the following areas:

IN 1.1.1 Site information needed to calculate the release of radionuclidesto the accessible environment.

DRAFT SCP 123 -9- 9:53 am 08/26/86

IN 1.1.4 Calculational models to predict radionuclide released to theaccessible environment.

IN 1.1.5 Determination of the radionuclide releases to the accessibleenvironment associated with representative scenarios.

IN 1.1.6 Probabilistic estimates of the radionuclide releases to theaccessible environment considering anticipated and unanticipatedscenarios.

Issue 1.8

Issue 1.9

IN 1.14.5

IN 1.14.6

IN 1.14.7

Can the demonstration of favorable and potentially adverseconditions be made as required by 10 CFR 60.122?

(a) Can the higher-level findings required by 10 CFR Part 960, bemade for the qualifying condition on the postclosure systemguideline and the disqualifying and qualifying conditions on thetechnical guidelines for geohydrology, geochemistry, rockcharacteristics, climate changes, erosion, dissolution, tectonics,and human interference; and (b) can the comparative evaluationsrequired by 10 CFR 960. 3-1-5 be made?

Radionuclide retardation by precipitation processes along flowpaths to the accessible environment.

Radionuclide retardation by dispersive/diffusive/advectivetransport processes along flow paths to the accessible environment.

Radionuclide retardation by all processes along the flow paths tothe accessible environment.

Most of these uses are performance assessment calculations, with theexception of demonstrating the favorable or adverse conditions in 10 CFR Part60.122. Data from this information need are used directly to address the siteconditions in sec. 60.122. The information is used in confirming theperformance allocation for radionuclide retardation in the Calico Hills tuff(see 8.3.5. ). The assessments of transport and retardation alongpotential flow paths are described in more detail in discussions of issueresolution strategy (sec. 8 ) and performance assessments (sec. 8.3.5 ).

8.3.1.3.4.4 Schedule and milestones

The schedule of reports on the data generated in thisgiven below.

information need is

Number Level Descriptive Title Delivery Date

R31

R309

R720 II Interim report: letter report on 3/87sorption isotherms

R396 II Report on effects of microbial activity 6/87on retardation

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R395 I I Sorption model complete 9/89

R383 II Summary report on sorption of radio 9/90nuclides by microbes

R382 II Report: sorption on particulates 9/90

M376 I Final report on sorption at Yucca 9/90Mountain

The primary use for sorption data is to support performance assessmentcalculations of radionuclide transport and retardation. The chart below showsthe relation of the reports listed above to the schedule for major performanceassessments that use these data. Gathering sorption data has been an ongoingactivity and will continue throughout the site characterization phase ofrepository development. Also shown on the hart are some importantconnections with other program elements that supply samples or information tothe sorption work, more specifically the drilling activities that supply tuffsamples, and the development of ground water composition data for unsaturatedzone ground waters (from IN 1.14.1.2), and waste form dissolution studies.

(Develop a PERT chart (example below) showing the performance assessmentmilestones using sorption data, the report numbers given above, the drillingschedule for holes likely to supply samples of Calico Hills tuff, and theunsaturated zone water composition from IN 1.14.1.2.]

DRAFT SCP 13 -12 9:53 am 08/26/86

PERT chart

DRAFT SCP 123 -13- 9:53 am 08/26/86

PERT CHART SHOWING IN1:14.4: MILESTONES AND MAJORRELATIONS WITH PERFORMANCE ASSESSMENT, WASTE PACKAGE

AND DRILLING MILESTONES

PERFORMANCE ASSESSMENT MILESTONES

WASTE PACKAGE DISSOLUTION MILESTONES

SAMPLE AVAILABILITY FROM DRILL CORING OR SHAFT

REPORT NUMBERS AND DATES FROM THE MILESTONE LIST

8.3 LEVEL OF DETAIL FOR PLANS 8/27-28/86

SAMPLE PROVIDED BY HQ/WESTON TO ADDRESS APPROPRIATE LEVEL OF DETAIL FOR SCP

NNWSI PRECLOSURE TECTONICS INFORMATIONNEED DESCRIPTION

8.3.1.17.3 Information Need 4.9.3. Ground motion at the site from potentialman-made or natural seismic events

8.3.1.17.3.1 Technical basis for addressing the information need

Link to the Technical Data Chapters

List the section of Chapter 1 where the known information was summarized,or where more information required was identified. (Examples)

Section 1.4.1.2 Identification of seismic source zonesSection 1.4.1.3 Evaluation of earthquake potential of seismic source

zonesSection 1.4.1.5 Recurrence intervals for seismic sourcesSection 1.4.2.1 Vibratory ground motion for designSection 1.4.2.3 Evaluation of weapons testing on estimates of ground

motion and faulting

Parameters (Data. Analyses and Models Required)

List the data to be collected for this information need, or supplied from

other information needs, the data analyses required, and any model developmentrequired. (Examples)

Data to be gathered in this information need:

Surface and down-hole recording of microearthquakes.Surface and down-hole recording of weapons testing.Surface and down-hole recording of strong-ground motion.In-situ material properties of soil under surface facilities.

Data Analyses:

Identification of seismic source zones using earthquake locations, faultplane solutions, association of earthquakes and faults, fault trenchingstudies, and tectonic model development.

Evaluation of earthquake recurrence parameters for each seismic sourcezones.

Attentuation properties (Q) to be used for evaluated strong ground motionin the southern Great Basin.

Probabilistic assessment of vibratory ground motion for surfacefacilities.

Deterministic assessment of vibratory ground motion for surfacefacilities.

DRAFT Licensing 175 -I- 3:31 pm 08/12/86

vibratory ground motion for subsurface facilities.

Assessment of vibratory ground motion from weapons testing using maximumyield of weapons tests at the various testing areas on the TS.

Compilation/Evaluation of strong ground motion using empirical equationsand actual data to be used to assess vibratory ground motion.

Model Development:

Tectonic model for Southern Great Basin (see section 8.3.1.8, InformationNeed 1.19.2).

Data supplied from other information needs:

Location of Quaternary faults (1.19.2)Trenching of Quaternary faults (1.19.2 and 4.10.2)Recurrence Intervals and Slip Rates for Quaternary faults (1.19.2 and4.10.2)

Logic

Explain the logical tie among the parameters and information items. Thediscussion could include the following three areas.

Overall purpose and Objective of the IN - Briefly explain the purpose ofthis information need and the objectives of the studies. As an example:

The purpose of this information need is to assess the seismic hazard ofthe site to properly evaluate the design vibratory ground motion forstructures, systems, and components that are important to safety orisolation. This includes both surface and subsurface facilities. Theevaluation of vibratory ground motion will include both natural earthquakesources for the site and southern Great Basin region and weapons testing onthe Nevada Test site. Data will be gathered to help support and satisfyperformance allocation for preclosure design issues 4.4, evaluating iftechnology is adequate to construct, operate and decommission the repository.The result of this information need will be a statement of the vibratoryground motion (peak acceleration, peak velocity, associated time histories andresponse spectra) that the repository facilities will be designed to withstand.

Technical Relationships - Explain the ties among the data to be gathered,data supplied by other information needs, analyses of data required by theinformation need and needed model development. As an example: Explain thatthe evaluation of vibratory ground motion integrates data and analysis fromthree subtopics; 1) seismic sources: 2) earthquake potential and recurrenceparameters; 3) ground motion attention relationship. The data to be gathereddirectly inputs to each of these three areas. Two general methods will beused to evaluate vibratory ground motion. The first method, generally labeledas deterministic, will determine in a discrete fashion if a seismic source isactive, if active what its earthquake potential is, and estimate the vibratoryground motion given the closest approach of the source and its earthquakepotential. The second method, labeled as probabilistic, will determine in acontinuous fashion (likelihood and uncertainty) all potential seismic sources,

DRAFT Licensing 175 -2- 3:31 pm 08/12/86

occurence parameters (likelihood of different sized earthquakes) andattentuation equation, and will derive the probability of exceeding many

levels of vibratory ground motion. Both approaches will be used to complementand check the other in developing vibratory ground motion for design.Components of each of the three sub-topics is outlined below.

A. Seismic Source Zones

1. Define Natural Sources - Area Sources and Faults

2. Relate seismicity to structure - Using earthquake locations,focal mechanisms, fault offsets, amount of seismicity andearthquakes cross sections.

3. Define Weapons Testing Sources - Areas that may be used in thefuture.

B. Recurrence Parameters for Each Source

1. Compile historic and instrumental seismicity including earthquakelocations and magnitudes.

2. Define catalog completeness (equal probability of detection andlocation of events for given area).

3. Using geologic data on faults, define ages of offsets, calculateslip rate for each fault.

4. Compile regional and, local estimates of strain rate from geodeticmeasurements.

5. Calculate recurrence parameters for each source includingactivity rates, slope of recurrence curve, upper magnitude cutoff.

6. Define maximum yields of potential weapons testing events.

C. Vibratory Ground otion

1. Surface Facilities

a. Compile world-wide empirical relationships and data.b. Attenuation rates for southern Great Basin.c. Potential for site amplification at surface facilities.d. Calculate ground motion attentuation equations for weapons

test events using empirical data.e. Determine site specific ground motion equation/relationships

for natural events.

2. Sub-surface Facilities

a. Compile downhole empirical data from TS weapons tests andmicroearthquakes.

b. Compile subsurface data (worldwide).c. Compute transfer function surface/sub-surface.


Technical approach for the studies under this Information Need

Explain the technical approach(s) used to define and/or bound the amountof testing and data analysis required.

This explanation will require a discussion of the degree of vibratoryground motion needed in the design process (ie., the strategy for design)Deteministic estimates will be based on site data identifying the seismicsources which will control estimates of ground motion. The probabilityresults will also help identify the most important seismic sources.Deterministic ground motion will be based on median magnitude for each sourceto derive a median estimate of vibratory ground motion. The probabilisticresults and geologic studies will support the adequacy (conservatism) of thedeterministic results.

8.3.1.17.3.2 Planned studies, tests, and analyses

List the hierarchy of studies and subordinate activities to be describedin the following text. Briefly explain the reasons of the aggregation given.

8.3.1.17.3 Earthquake Monitoring Studies

(The following text is intended as an example of the content of a studydescription - only one activity treated for this example.)

In the text, in arative form, explain:

- the objectives of the study - i.e., to record the ongoing seismologiccharacter of the NTS region including both natural earthquake andweapons tests.

- analyses the data supports - the data will be used to identify activeseismic sources, to calculate recurrence intervals for each sourcezone, evaluate the transfer function between the surface andsubsurface, and will assist in developing postclosure disruptiveevent probabilities.

- indicate the technical approaches to be used to produce defensabledata, i.e., calibration of instruments, make sure weapon tests havecompressional first arrivals.

Activities planned for this study include: 1) operate regional seismicnetwork and monitor earthquake activity; 2) install and operate surface andsubsurface strong motion instruments; 3) evaluate regional ground motioncharacteristics.

(One Activity Described Below)

Activity 1.17.3.1 Operate Regional Seismic Network and MonitorEarthquake Activity


Objectives

State objectives of this activity - i.e., to record and locate alldetectable earthquakes in the Yucca Mountain region with the emphasis onaccurately evaluating earthquake size and location precision to determine ifrecorded earthquakes can be correlated with specific structures or faults.

Parameters

Earthquake hypocenters (latitude, longitude, depth)Earthquake magnitudeEarthquake fault plane solutionsEarthquake source mechanisms (moment, stress drop)Crustal Attentuation Properties

Data Needed - Accurate crust and upper mantle velocity for the YuccaMountain site and southern Great Basin.

Description of the activity (examples)

* Show on a map the location of seismographic stations.

* Specify the type and number of stations.

* Specify the method of locating events (ypo 71, ypo-ellipse)

* Specify the precision desired and accuracy of picking arrivals.

* Specify the method used to determine focal mechanisms.

* Specify how magnitudes are determined.

* Discuss how regional attenuation properties are determined (amplitudevs. distance).

* Specify velocity structure used and discuss plans to update or revise.

Describe the methods and technical procedures to be used.

8.3.1.17.3.3 Where this information will be used

This information will be used to help develop estimates of the seismichazard for the Yucca Mountain site. The location and focal mechanisms ofearthquakes will be used to help identify seismic sources. The number andmagnitude of events will be used to develop earthquake tecurrencerelationships for each identified seismic source.

8.3.1.17.3.4 Schedule and Milestones


Information Need 4.9.3 Ground otion at the Sitefrom potential man-made or natural seismic events

Study 4.9.3.1

Activities

Study 4.9.

Activities

Study 4.9.3.3

Activities

Seismologic Data Compilations

Regional seismologic Networklocation, magnitude, fault plane solutions,surface, downhole, source mechanisms

Local Accelerometer Networksurface, downhole, for analysis ofunderground, surface transfer function

Material Properties at Surface Facilitiessoil borings, depth to bedrock (refraction) densityshear velocity, compressional velocity

Methodoloy to Identify Natural versusMan-Made Events (including Aftershocks)

post weapons tests and aftershockidentification, fault offset

Evaluation of Seismotectonic Sources and EarthquakeRecurrence Intervals

Identify Natural Seismotectonic Sourcescorrelations of earthquakes to faults,area sources, fault sources (using resultsfrom trenching postclosure)

Evaluate the arthquake Potential of NaturalEarthquake Sources

recurrence intervals, completeness of catalog,slip rate, strain rate, fault dimensionparameters, maximum magnitude

Define Effects of Weapons Testing on Earthquake Occurrenceclean up catalog, remove weapons

Define Locations and Yield of Potential Weapons Testingyield limits, potential areas of weapons

Develop Estimates of Vibratory Ground Motion

Evaluation of Regional Ground Motion Characteristicsamplitude versus distance, Q effect onmagnitude determination

Evaluation of Great Basin Source Effects onEstimates of Vibratory Ground otion

world-wide data (tensional versus compressional)theoretical estimates, degree of conservatism

Develop Attenuation Equation For Weapons Testingempirical data, site effects, dispersion

Strong Ground Motion Models Analysisempirical data, attenuation equations,site specific spectra (scaling), theoreticalmodeling

Develop Procedures to Estimate UndergroundVibratory Ground Motion

world-wide data, NTS data, theoreticalmodeling

Evaluate Potential For Ground MotionModification at Surface Facilities

computer modeling, strong motion datasite data (earthquake and weapons)

Study 4.9.3.4 Develop Design Basis Vibratory Ground Motion Methodology

Activities Probabilistic Hazard Evaluationsmultiple inputs, sensitivity of all parameters

Deterministic Hazard Evaluationsfor significant seismic sources

Methodology to Determine VibratoryGround Motion for Design

how probabilistic and deterministicwill be combined

Test Plan:G-Tunnel Welded Tuff Mining Evaluations

by

Roger M. ZimmermanNNWSI Geotechnical Projects DivisionSandia National Laboratories

Albuquerque, New Mexico

SNL Keystone Document6310-85-7

August 1985

Sign Off Sheet

Prepared by

Reviewed by

QA Approval

Division Approval

Department Approval

Roger M.Zimmerman

Arthur J. ansure

Gary Romero

Thomas Blejwas

Thomas 0. unter

Date

Date

Date

Date

CONTENTS

PAGE

I. Introduction 1

A. BackgroundB. Purpose

II. Scope, Objectives and Rationale 3

A. Scope 31. Location 32. Phases

B. Objectives 7C. Rationale

III. Experiment Details

A. Pre-WTM Activities1. Excavation2. Drilling 163. Permeability Measurements4. Instrumentation Installation5. Preliminary Design ModeLing

B. WTM Measurements 191. Control Blasting2. Drift Convergence Measurements 203. Drift Stabilization4. Drift Convergence Monitoring 26

C. Post-WTM Activities1. Permeability Measurements2. Drift Monitoring 303. Numerical Model Evaluations 304. Other Testing 32

D. Instrumentation - Continuous Recording 321. ultipoint Borehole Extensometer 322. Rock Bolt Load Cells 353. Borehole Stressmeters 35

E. Instrumentation - Discrete Measurements1. Permeability2. Borehole Deflectometer 363. Rod Extensometer 374. Hydraulic Pressure Cells 37

r. Data Acquisition System1. Continuous2. Discrete

G. Instrumentation CalibrationH. Laboratory Tests 43

-ii-

s

CONTENTS (Continued)

IV. Experiment Management

A. Responsible PersonnelB. ScheduleC. Documentation 45

D. Quality Assurance 47

E. Safety 49

V. Experiment Evaluations

A. ObjectivesB. Expected Results

VI. References 56

-iii-

LIST OF FIGURES

Figure Page

I. Proposed Enlargement of the -Tunnel Underground Facility 4

2. Cross Sections at Ends of Proposed Demonstration Drift SectionsShowing Stratigraphy

3. Layout Details

4. Drilling Patterns and Instrumentation Placement

5. Concept for Concrete Insert 29

6. GTUF Data Acquisition System 39

7. Mining Evaluation Planning Schedule 46

1. ITRODUCTION

A. Background

Yucca Mountain on the Nevada Test Site (NTS) is comprised of a thick

sequence of volcanic ash-fall and ash-flow tuffs. This mountain s being

considered as a ite for a nuclear waste repository, and feasibility studies

for this purpose are being conducted by the Nevada Nuclear Waste Storage

Investigations (WSI) Project. C-Tunnel, located in Rainier Mesa on the

NTS, intersects layers of welded and nonwelded tuffs that have similar thermal

and mechanical properties and stress states to the tuffs in Yucca

Mountain. The availability of this tunnel for immediate field experi-

mentation allows Sandia National Laboratories (SNL), a participant in NNWSI,

to conduct field characterizations of tuffs without expensive excavation and

facility development costs.

A suite of field experiments has been planned for G-Tunnel. These are

to be contained within a dedicated region at the end of the tunnel. This

region s called the G-Tunnel Underground Facility (GTUF) and excavations

extend into welded and nonwelded tuffs. The purpose of GTUF is to provide

opportunities to develop and conduct field experiments designed for evaluation

of rock mass phenomena of these tuffs. The welded tuff mining (WTM) evalua-

tions discussed in this document are the capstone effort planned for GTUF and

consist of making welded tuff rock mechanics measurements and performing

evaluations needed to ensure that technologies are adequately developed prior

to testing in the Exploratory Shaft at Yucca Mountain. Major repository in

situ site characterization development efforts are planned in Yucca Mountain

in welded tuff with the excavation of the Exploratory Shaft.

B. Purpose

The purpose of the G-Tunnel welded tuff mining evaluations is to utilize

GTUF to conduct an evaluation of the rock mass behavior caused by excavation

of a relatively short room, sized to dimensions representative of drifts that

could be used for the horizontal emplacement concept being considered for

storage of commercial high-level nuclear wastes in tuff. The construction of

the special room will demonstrate the technical feasibility for mining and

stabilizing this size drift in welded tuff, and measurements taken in and

around the drift will be used to evaluate practices and instrumentation use

planned for a similar sized room in the Exploratory Shaft.

Experiment test plans in tuff are benefitted by a brief description of the

depositional and cooling processes. Tuffs are deposited because of sudden

volcanic eruptions, and the resulting ash either falls or flows into

sheet-like deposits. When the depositional temperatures and lithostatic pres-

sures are sufficient, welding results. Welding, a textural term, is identi-

fied primarily by the pore space. Inherent in the formation of the tuffs

is shrinkage due to cooling. This cooling causes the formation of joints in

the hardened rock mass. Welded tuff is more jointed than nonwelded tuff, and

investigations in this medium are needed to determine the effects of the

joints on the overall rock mass properties.

A special feature in this testing is that measurements are to be made in a

jointed rock during the excavation process. This is the first time that this

has been done in either welded or nonwelded tuffs, and these evaluations

should bring out the salient features pertinent to construction-related

measurements in tuffs.

-2-

II. SCOPE, OBJECTIVES, AND RATIONALE

A. Scope

1. Location

The welded tuff mining evaluations are to be an extension of the existing

GTUF. Figure 1 shows a plan view of the region. A mining evaluation is to

occur during the construction of the demonstration room, but mining is

required in the U12g.12 drift prior to the actual WTM evaluation so that

instrumentation can be set in place and measurements can be taken prior to.

during, and after the actual mining of the room. Figure 2 shows elevation

views of the region where the new mining would occur. The principal

stratigraphic features of the welded and nonwelded tuff are shown. The

general stratigraphic variations are:

Upper transition - partially to moderately welded tuff

Welded tuff - moderately welded tuff, densely welded tuff,

with greenish-yellow clay lenses.

Lower transition - rubble zone and vitric welded tuff

Nonwelded tuff - zeolitized ash-fall tuft

The thickness of the units from the top of the upper transition to the

bottom of the lower transition is approximately 16 m.

2. Phases

a. Pe-WTM Measurements. Pre-WTM activities consist of the mining of

the U12g.12 extension in the nonwelded tuff and later diamond core

drilling and measurements taken from that drift. During the mining of the

U12g.12 extension, drift-convergence measurement techniques are to be

evaluated.

Figure 1. Proposed Enlargement of the G-Tunnel Underground Facility

CROSS SECTION AT ENDOF PROPOSED DEMONSTRATION DRIFT

Figure 2. Cross Sections at Ends of Proposed DemonstrationDrift Sections Showing Stratigraphy

Mining will be temporarily halted and vertical and horizontal drift

convergence measurements will be made at eight stations along the drift to

review planned measurement techniques.

After mining, 12 holes are to be diamond drilled from the Ul2&.l2

extension into the unexcavated rock where the WTM is to occur. Six of the

holes are to be used for borehole permeability measurements. Straddle packer

units are to be located at sequential positions along the boreholes and

pressure-flow rate measurements are to be made so that a permeability profile

can be established for each hole. The process is to be repeated after the WTM

so that the effects of fracturing caused by the blasting or rock mass stress

redistri- bution can be detected. The other six holes are to contain

instrumentation to be monitored during the WTM. Two of the holes are to

contain borehole stressmeters (BSM) and the other four are to be used to

monitor progressive angle changes n the rock mass as the mining face

advances. Details of these and other measurements are discussed in Section

III.

Two holes are to be percussion drilled from the Ul2g.12 drift up towards

the WTM area. Multiple point borehole extensometers (MPBX) are to be

installed in the holes for the purpose of (1) evaluating MPBX installation

techniques and (2) later measuring the relative displacements between the two

drifts. Details are discussed in Section III.

b. WTH Measurements. This phase consists of two sets of measurements

taken during the mining in the welded tuff. One set of measurements will

be a semiquantitative set associated with an evaluation of mining

techniques.

6-

Drilling patterns, explosive placements, fuse delay patterns, and resulting

measurements of the limits of the blasting will be periodically evaluated

during the mining. The second set of measurements consists of determinations

of drift convergence phenomena during the sequential mining activities. The

emphasis will be to monitor the rock mass behavior as the tuff is excavated.

Analyses wll include numerical model evaluations.

c. Post-WTM Measurements. This phase consists of all measurements

taken after the demonstration room has been excavated and stabilized.

Measurements will include determining changes in the rock mass behavior

with and without drift stabilization using rock bolts. The permeability

profile will be repeated in the remaining rock so that blast effects can

be assessed. General postmining rock mass behavior will be moitored as a

function of time and a rock mass displacement and rock bolt force

measurement system will be available to support other nonspecified testing

activities. Also, hydraulic pressure ells (Cs) will be installed in

special concrete fixtures to evaluate instrumentation placement and

structural interaction effects.

B. Objectives

The objectives for the evaluations are to:

(1) Review relevance of standard rock mass rating techniques for use

in defining stabilization procedures for a repository-sized room in welded

tuff.

(2) Apply control blasting techniques in construction of a room in

welded tuff for subsequent evaluations and recommendations for Exporatory

Shaft efforts.

-7-

(3) easure and evaluate drift convergence phenomena to determine the

responses of the welded tuff to minimum

(4) Perform 2-D numerical model calculations of the repository-sized

room and compare results with the measurements in objective (3) to

determine reasons for any differences.

(5) Evaluate instrumentation installation techniques and resulting

measurement results to improve measurement capabilities.

(6) Serve as a test facility for supplemental rock mechanics testing

(i. e., plate-loading testing, possible demonstration of horizontal boring

machine).

C. Rationale

Objective (1) serves as a review of applications of standard mining

technology. The room is to be mined and stabilized using standard underground

support designs consistent with NTS safety requirements. Designs shall

include evaluations of the rock mass with standard rock mass classification

7systems, CSIR and Q-System. The construction of the room will be the

first of its type in welded tff, and the establishment of the room will serve

to provide NNWSI engineers with a prototype verification of a repository-type

design. The construction of the room relates to NMWSI Information Needs 4.7.1

and 4.7.8 in a generic sense.8 These Information Needs relate to

stabilizing underground openings. In particular, the construction of the room

demonstrates that the underground facilities in welded tuffs can be

constructed with reasonably available technology. The construction of a

repository-sized room (width 6.1 m, height 3.7m) in similar stress fields

-8-

first in G-Tunnel and later at the Exploratory Shaft provides documentation

that the underground design concept using a relatively wide room is feasible.

The width of 6.1 m has been selected as a compromise for repository design

considerations. Currently, drifts 5.5 m (18 ft) wide are being onsidered for

spent fuel storage, but wider alcoves will be cut at the actual canister

emplacement locations. Drifts 7.9 m (26 ft) wide without alcoves are being

considered for commercial high-level waste storage. The 6.1 m (20 ft) width

is acceptable to repository designers for the purposes intended.

The construction of the demonstration room also relates to Nuclear

Regulatory Commission (NRC) regulations in 10 CFR 60. A potentially

adverse RC condition that ust be evaluated at Yucca Mountain s to ensure

that there are not "geomechanical properties that do not permit design of an

underground opening that will remain stable through permanent closure."

(60.122) The construction of the room in G-Tunnel provides for an early

assessment of the underground design concept.

In a discussion of the Q-System for underground support design, it was

pointed out that estimates of supports are required in three stages in a

project: for the feasibility studies, for the detailed planning, and finally

during excavation itself." The evaluation of the performance of the welded

tuff in -Tunnel will serve as a major factor in preparing for the detailed

planning stage for Yucca ountain because NWSI mining engineers will then

have a prototype facility to relate designs to.

-9-

Objective (2) addresses control blasting evaluations. NRC 10 CFR 60

(60.133) requires that "openings shall be designed to reduce the potential

for deleterious rock movement or fracturing of overlying or urrounding

rock." Also, "the design of the underground facility shall incorporate

excavation methods that will limit the potential for creating a preferential

pathway for ground water." The monitoring of the damage through inspections

of blast effects during the mining and the preand post-WTM fracture

permeability evaluations addresses these two requirements. Results from these

studies serve as benchmarks for similar evaluations planned for the

Exploratory Shaft.

Objective (3) deals with the measurement of drift onvergence phenomena.

NNWSI Information eed 4.7.4 calls for determining the potential impacts of

rock characteristics on a repository design. The in situ stress state in

G-Tunnel is similar to that expected at Yucca Mountain because the tunnel has

a 430-m overburden and the horizontal stress state appears to reflect the

regional trends. Within the technology of rock mechanics, there is a

philosophy that "monitoring the behavior of underground excavations under

construction is the most reliable aid in the design and construction of rock

tunnels and chambers." Drift convergence displacements are indicative of

either stable or potentially unstable behavior. Three factors are

significant:12

(1) Magnitudes of displacements.

(2) Rates of displacements.

(3) Displacement capacities of the support system and the rock mass.

10-

Reference 2 with documentation from Reference 13 states that "when

displacements exceeded the predicted elastic displacements by a factor of 5 or

10, the excavation and support procedures had to be modified to prevent

further large movements." Most of the large displacements were on the order

of 12 to 75 mm. Similar data for welded tuff do not exist, and the proposed

testing would provide this data. "Experience shows that rates of displacement

on the order of 0.001 mm/day indicate stable conditions, rates of 0.05 mm/day

are quite high and dangerous for wide chambers, while rates of over 1.0 mm/day

are excessive and call for additional upport measures." From the

capacity standpoint, excessive displacements can result in failure of

shotcrete or rock bolts, which are common light-duty support systems.

"Displacements should also not exceed the capacity of the rock mass to

maintain its strength and coherence since rock strength along joints decreases

with displacement as irregularities on the joint surface are sheared or

overridden."

Objective (4) deals with a model evaluation of the drift convergence

phenomena. This model evaluation effort is not a model validation. The

variations in stratigraphy of the welded tuff over a relatively short distance

of 16 to 20 m provides sufficient warning to cause caution about overpre-

dicting model-measurement comparison agreements. Premining predictions for

the record are not planned. Premining elastic calculations will be made to

determine the instrumentation sensitivity requirements. The 2-D jointed rock

model will be made available prior to the actual mining but not until after

the mining is completed will the final model be completed. Included in the

mining is a fracture-mapping effort. Results from the mapping will be incor-

porated into the model for use during the analysis and model-measurement

-11-

evaluation period. Results from this evaluation effort should provide key

information required to perform a model validation in Exploratory Shaft

testing.

Data from Objective (3) will play a prominent role in the evaluations.

The need for a model evaluation is defined by the NRC in its requirements for

a Safety Analysis Report (60.21). In particular, "analyses and models that

will be used to predict future conditions and changes in the geologic setting

shall be supported by using such methods as field tests . . . which are

representative of field conditions, monitoring data, and natural analog

studies." Models require groups of data describing the real system and must

contain descriptions of the system geometry, rock mass stratigraphy, data on

material properties, and descriptions of load distributions.1

Objective 5) deals with the acquisition of experience with

instrumentation and measurements. uch of the proposed instrumentation has

not been used in construction-related activities in tuff, and this evaluation

provides the opportunity. Since some instrumentation must be used close to

the mining face, there is a need to evaluate the performance of the instru-

ments in the proximity to the blasting. There s also a need to develop

measurement techniques for all phases of testing. In particular, the fracture

permeability profiles have not been used for this purpose; thus, reliable

techniques must be developed.

Objective (6) is dedicated to overall NNWSI project efficiency. The

construction of a demonstration room with repository-size dimensions in welded

tuff provides other researchers with an opportunity to make measurements in an

-12-

environment similar to that expected in Yucca Mountain. A plate-loading test

is planned for the Exploratory Shaft, and the demonstration room would serve

as an excellent facility to establish field procedures. Canister-scale boring

machine evaluations are being considered.

III. EXPERIMENT DETAILS

A. Pre-WTM Activities

1. Excavation. Figure 3 shows the layout details for the excavations.

Pre-WTM excavations pertain to the extension of U12g.12. The drift is to

terminate 26 from a plane running through the end of the present

Extensometer Drift. The dimensions of the drift are 3.7 x 3.7 m. The lower

drift is to be mined with an Alpine miner and stabilized with rock bolts and

wire mesh. The drift is to have an upward slope of 0.5 percent, which is

normal for drift construction on the NTS.

Figure 3 shows locations for measurement stations in the Demonstration

Drift, which are identified as sections A through . The figure shows typical

anchor locations for the U2g.12 drift convergence measurement evaluations.

Anchor posts made from rock bolts, approximately 0.5 m long, are to be bonded

to short percussion-drilled holes. The anchor posts are to ontain eyebolts

suitable for tape extensometer measurements. A Terrametrics unit, model

50-SN820331-2 is to be used for the measurements. The dial gage can be read

to 0.0025 m. At least eight measurement stations will be selected along the

drift. Actual locations will be coordinated as the mining advances. Emphasis

will be on placing the anchors so they will last during the mining and provide

reliable measurements. Records will be kept as to the locations of the

station of the mining face and the station of the last row of rock bolts, so

that effects of excavation and drift stabilization can be discerned.

-13-

PERMEABILITY AND BOREHOLE STRESS HOLES

PERMEABILITY AND ROCK BOLT

Figure 3. Layout Details

2. Drilling. Figure 4 shows the drilling pattern for pre- and post-WTM

activities. Twelve Pre-WTM holes will be diamond drilled with core recovery

from the U12g.12 extension. Cores will be logged and standard geological

inspections made. The holes will be drilled in three planes, identified by

sections B D, and F in Figure 3. Two permeability holes are to run through

the 1/4 points, within ±0.5 m, across the width of the demonstration room at

each section. The stressmeter/deflectometer holes are to be within 1 m ±0.25

m of the corners of the room. Holes will have to be aligned after field

surveys of the U12g .12 drift has been completed. The permeability-holes will

be nominally 24 m long and the others 19 .

3. Permeability Measurements. A single borehole permeability measurement

can be made by isolating a test interval with straddle packers and performing

steady-state pressure-flow rate measurements in the interval. Flow measure-

ments in jointed rock are dominated by joint or fracture effects. This flow

is sensitive to the aperture dimensions, spacings, and asperities. Estimates

of pereabilities for flows dominated by joint effects can be determined using

analyses of flows between parallel plates. Fracture or joint flows in

packed-off boreholes are represented by an equation that describes hydraulic

conductivity in cm/s. This equation is:5

where

Figure 4. Drilling Patterns and Instrumentation Placement

A necessary calculation is determining the aperture dimension from the flow

measurements. This is accomplished with the following equation:

where

Use of re- and postmining permability measurements for mining evaluations

is being developed in this experiment. A portion of Equation (2) is extracted

to form the key quantity to be used in these evaluations. The quantity

is called the hydraulic quotient . The Q and quantities

are measured directly with the permeability testing apparatus. Experience has

shown that the determination of the quantity n is difficult in tuff. We

do not plan to try to measure the quantity n in this testing because we are

trying to use the permeability testing as a diagnostic aid to show changes due

to the mining activities. The plan is to determine the quantity for

successive intervals, nominally 0.6 m long, in each of the test holes for the

pre- and postmining conditions. The establishment of the profile was outlined

by Hodkinson. The HQ quantities will be plotted a a function of length

of the holes for the two conditions and differences will be observed and

analyzed. It is expected that the mining activities associated with the

-17-

mining of the demonstration room in the welded tuff will cause disturbances in

the rock mass around the opening nd that these disturbances will appear as

changes in the HQ quantities. These profile comparisons should also provide

documentation as to the limits of the zone disturbed by the mining.

The principal equipment used with these tests onsists of a pair of

straddle packers suitable for use in holes, a turbine water pump, a

nitrogen tank with a regulator used to inflate the packers, a manifold that

regulates flow into two pipes, a water meter that measures flow, and a

pressure gage. The straddle packers are to be designed so that the test

interval is approximately 0.5 m long.

The profile is to be established by performing pressure-flow rate

measurements at 0.6-m intervals along the length of each borehole located in

the welded tuff. Measurements will be taken at five different pressures.

nominally 0.3, 0.6, 0.9, 0.6, and 0.3 MPa, at each measurement station along

the borehole. The packers will be deflated, the assembly will be translated

0.6 m, and the five-pressure measurement process will be repeated.

4. Instrumentation Installation. Three types of instruments will be

installed or used in the remaining holes. Borehole Stressmeters (BSM) will be

installed at Section D and tubing for a Borehole Deflectometer (D) will be

installed at Sections B and F (Figure 3). Details for these sensors will be

discussed in Section III.D. The BSMs will be located approximately as shown

in Figure 4. Precise location will be established after the numerical

-18-

calculations have been completed and convenient measurement points located.

Borehole fracture patterns will also be considered prior to placement. BSMS

will take measurements in the vertical plane. BDM tubing will be installed,

and the BDM will traverse the length of the holes to initialize the

measurements. Figure 4 also shows the locations of MPBX holes planned for the

premining efforts. MFBX holes are to be percussion driven from the U12g.12

drift to the base of the Demonstration Drift. Four anchor MPBXs Type D

(Section III.D), are to be placed in the holes, with anchor locations being at

1 m intervals starting from the ends of the holes nearest the welded tuff.

MPBX and BSM instrumentation will be connected to the DAS prior to the

initiation of the mining in the Demonstration Drift.

5. Preliminary Design Modeling. Finite element calculations have been

made to evaluate the sensitivities of the instruments planned for use. A

linear elastic model in the computer code JAC was used in the calculations.

The calculations were used to establish the feasibility of the borehole

deflectometer measurements and to provide guidance as to expected ranges for

drift convergence measurements. These calculations indicate that maximum

angle changes could be as high as 80 s over a 1-m length. The instrument

selected has a sensitivity of 2 s. These calculations also indicated that

the total magnitude of the vertical drift convergence could be as high as 7 mm.

B. WTM Measurements

1. Control Blasting. Control blasting techniques will be established and

evaluated by an outside consultant, who will specify drilling patterns,

explosive loading patterns and quantities, and fuse lengths. The blasting

-19-

round will be detonated and the consultant will inspect the excavated area,

and make recommendations for changes before work starts for the next round.

It is expected that the blasting techniques along the drift length will

improve with this experience. The goal for the control blasting evaluation

will be to recommend control blasting techniques for the Exploratory Shaft.

A feature in the control blasting studies will be evaluations of different

drilling patterns or blast conditions at stations B, D, and F. These are the

stations where permeability profiles are to be taken, and it is desirable to

relate mining methods to those measurements.

2. Drift Convergence Measurements. The principal purpose for these

measurements is to document the drift convergence during the excavation

stage. An expected output from the measurements is a definition of the rate

of drift convergence for the welded tuff for conditions with the addition of

rock bolts and wire mesh.

As soon as a round has been detonated and the muck cleared away at

stations C and E (Figure 3), a team will begin percussion-drilling holes 15 m

deep for placement of multipoint borehole extensometer (MPBX) anchors. The

holes will be oriented as shown in Figure 4. Six anchor MPBXs will be located

in four holes and installed according to manufacturer recommendations for

vertical and horizontal holes. Four anchor MPBXs will be installed in the two

off-vertical holes. The anchors will be located near the excavated surface

with measurements concentrated within 6 m. Actual anchor locations will be

selected based on the geological features found in the boreholes. Emphases

will be on taking measurements close to the drift surface. The collars will

-20-

be recessed into the surface so that a cover plate can be installed to protect

the sensors in a manner like that used in similar measurements taken during

shaft construction.

Four of the six-anchor extensometers are to be made by the same

manufacturer and are the ones proposed for Exploratory Shaft testing. The

extensometer deformations can be read with a dial gage or remote readout using

ultrasonic sensing techniques. Two pairs of other types of six-anchor

extensometers will be installed so that there will be in situ evaluations of

the advantages and disadvantages of each. The remaining four extensometers

are four-anchor units and will be located on both sides of the six-anchor

units.

Included in the fabrication of the heads of the extensometers will be

anchors that can be used for primary drift convergence measurements using a

rod extensometer. Vertical and horizontal measurements will be taken

immediately after the installation of the heads at the two stations. The MPBX

and rod extensometer measurements will be initialized, and work will then

commence on drilling for the next round. These measurements will be read

after the next three or four rounds or until the measurements stabilize, so

that desired excavation effects of rock removal can be ascertained.

For cross-drift measurement checking, the drift convergence measurements

taken with the rod extensometer will be compared with MPBX head ovements to

evaluate the compatibility of the measurements. f the deepest anchors for

the MPBXs are located sufficiently deep, then the relative head movements

should in fact be the displacements measured with the rod extensometer.

21-

As a companion study, measurements between the head and anchors of the

MPBXs can be used to determine the uniformity of the rock mass around the

opening. uch determinations are useful in model evaluations. The governing

equation is:

where

Equation (3) is useful because the borehole head-anchor measurements can

be made between two succeeding anchors and the modulus of deformation for that

interval can be determined. The use of differences in the displacements for

each anchor interval allows the analyst to perform calculations without

needing a quantitative description for the head movement.

Differences in displacements can be calculated for succeeding anchor

intervals from the collar to the deepest anchor, and the ross variation of

the modulus as a function of length along the boreholes can be determined.

These values will be ompared with those used in the modeling evaluations.

-22-

There s a possibility that a signigicantly reduced modulus should be used to

describe rock mass behavior for the first 1 or 2 m around a drift openin, and

these investigations should provide this information. An expected output from

these measurements and analyses will be a preliminary assessment as to

limitations on the applications of elastic theories to the behavior of welded

tuff. If necessary, nonlinear computer analyses will be initiated to study

the measured behavior to determine the dominant mechanisms contributing to the

observed rock mechanical behavior.

Efforts to establish estimates for the relaxed zone at each of the

measurement stations will be coupled with the analyses of the variations in

the modulus of deformation as a function of borehole length. These measure-

ments will be compared with pre- and postpermeability measurements to assess

whether they are compatible. If significant differences exist, they will be

investigated analytically and hypotheses formulated. These latter will serve

as important input conditions for designing the more elaborate Exploratory

Shaft experiments.

3. Drift Stabilization. The behavior of an opening in a rock mass

requiring partial support depends on the load-deformation characteristics of

the rock mass and the support. The interaction between a support and the rock

is the key ingredient to underground stability. The essential contribution of

the reinforcement is to assist the rock mass in supporting itself. any

underground openings have been stabilized with supports defined through

empirical methods. Successes in the designs of supports are attributed to the

effectiveness of geological investigations and on the ability to extrapolate

past experiences of support performances to new rock mass environments. A

-23-

method of extrapolating past experiences of support performance to new rock

mass environments involves, as a minimum rock mass classification systems.

The basic classification parameters are:

Strength of Intact Rock Mass

Rock Quality Designation RQD)

Spacing of Joints

Condition of Joints

Ground Water Conditions

Strike and Dip Orientation Effect

Rock Quality Designation (RQD)

Joint Set Number

Joint Roughness Description

Joint Alteration Number

Joint Water Reduction Factor

Stress Reduction Factor

Preliminary applications of these rock mass ratings for the welded tuff in

G-Tunnel indicate that the standup time for an unsupported roof span of 4.5

would be 25 to 605 days, and the maximum unsupported roof span or room height

would be 3.4 to .5 m. Results from both of these classification systems

suggest that the proposed span would be marginal as an unsupported span, and

cursory observations support the normal TS safety requirements for a minimum

of 3.6-m rock bolts at intervals of 1.2 m supporting an 11-gage wire mesh. A

-24-

factor not included in the rock mass classification systems is the occasional

man-made ground motion that occurs on the NTS, but short time experience

(30 yr) indicates that this type of support is adequate in tunnels onstructed

in a weaker nonwelded tuff.

To compare some of the rock mass rating results available for -Tunnel and

Yucca ountain should help show the relevance o the proposed testing to the

Exploratory Shaft efforts. Langkopf and Gnirk listed a range for the NGI

tunneling quality index Q-System) of 34 to 3.08 for the welded tuff in

G-Tunnel and 53.3 to 1.46 for the Topopah Spring Member in Yucca

Mountain. They listed a CSIR geomechanics classification of 60 to 80 for

G-Tunnel and 60 to 87 for the Topoah Spring Member. Dravo engineers evaluated

the Topopah Spring Member in another study and listed a CSIR geomechanics

classification range of 38 to 73 and Q system range of 25 to .06.

Differences between these two evaluations are not major, but the numbers do

show that there are significant differences in the predicted support

requirements. In the Dravo study, using the Q-system on the central block

considered for the candidate repository, it was pointed out that the round

supports could vary as a minimum from rock bolts and wire mesh to more

elaborate shotcrete systems with welded wire mesh and rock bolts. Obviously

there is need for better documentation of the behavior of welded tuff if we

are to predict behavior adequately for repository use.

The requirements for predicting drift performances for repository use

extend the state-of-the-art technology for predicting rock mass performance

because of the addition of heat and accompanying thermal stresses. Required

evolutional developments of this nature are based on a careful documentation

-25-

of the existing ambient temperature techniques and performance monitoring of

prototype-size drifts.

From an operational tandpoint, the freshly exposed surfaces of the

demonstration room will be mapped as the mining progresses. Details

appropriate for input into the two classification systems will be collected

and the rock mass ratings updated to reflect the most current conditions. The

deformation measurements before and after the placement of the rock bolts and

wire mesh will be analyzed to determine the influence of rock bolt performance

on drift convergence rates. Because of these needs, it is planned that the

rock bolting and wire mesh will be added ome 6 m behind the face as long as

NTS safety conditions permit. Unpublished mining experiences of the GTUF

Extensometer Drift suggest that this is feasible.

The eventual evaluations will relate the deformational responses of the

welded tuff to the rock mass classification systems so that a better pre-

dictive model can be established. Based n this model, recommendations will

be made regarding improvements necessary to improve predictive capabilities.

4. Drift Convergence Monitoring Included within drift convergence

monitoring will be a continual recording of drift convergence after the rock

bolts have been installed. It is hoped that the data trends before and after

the rock bolt installation will be sufficiently distinct so that re- and

postsupport drift convergence rates can be defined. If the rates are

extremely low, then measurement errors could mask the desired variations.

-26-

After the demonstration room has been excavated and the rock bolts placed,

rock bolt load tells (RBLCs) will be installed on rock bolts on each side of

sections C and E (Figure ). The purpose of these load cells is to monitor

changes in the rock bolt forces as the rock mass makes its final adjustments

to the excavated tate. It is not expected that the behavior will be

predictable, but it is hoped that possible nonuniform changes in rock bolt

forces an be related to expected deformation irregularities measured at the

sections. Analyses and correlations will depend heavily on the surface maps

of the region at these sections. Eight BLCs are to be added at each section

for completeness. Figure 4 shows the configuration.

HPCs are to be installed in the lining of the Exploratory Shaft.

Measurements with these cells are sometimes questionable, but they do

provide a measure of stresses within a broad tolerance band and these are the

data that are sought. Pressure measurements may not correlate with elastic

theories or even nonlinear numerical models, but measurements of general

magnitude provide proof that unexpected stress rise phenomena do not occur

around an opening. The main reason for installing the HPCs in the WTM is to

gain that experience for later use in Exploratory Shaft testing.

Since the main focus in the applications of the HPCs to the WTM is to

evaluate the installation measurements techniques in a mining environment, the

entire process is kept simple. A main feature in the installation of the HPCs

is to place them behind a form and then place concrete so that it envelop the

HPC. We are concerned about the falling concrete disturbing the PC placement

and also about the possibility of air pockets being formed around the HPCs.

-27-

Figure shows the testing concept that is planned for -Tunnel

simulation. A wedge shaped cavity is to be mined into two ribs of the

Demonstration Drift. The wedge can be removed with ordinary mining

techniques. The wedge will then be covered with a sheet of plywood and rock

bolted to the rock forming a cavity. The plywood will contain the HPCs, which

will be installed in a similar manner at is expected for the shaft liner at

the Exploratory Shaft. An opening will have been made in the top of the

plywood so that concrete can be placed to fill the cavity. After a 7 day

cure, the plywood will be removed and the rock bolts will be retightened to

the concrete surface. Thus a concrete insert is formed in the welded tuff.

The HPCs will be monitored as soon as is ractical after installation and

measurements will continue for a minimum of thirty days after installation.

Then miners will chip out the HPCs so we can determine an adequacy of the

installation and contact with the rock. From this, recommendations will be

made for future applications.

C. Post-WTM Activities

1. Permeability Measurements. Pre-WTM permeability measurements

procedures will be repeated in the welded tuffs surrounding the opening and a

revised permeability profile established. The pre- and post-WTM profiles will

be plotted and compared and differences investigated. The investigations will

be focused on defining the region around the opening that is disturbed by the

mining. Disturbances can be due to blasting and rock mass relaxation caused

by stress redistributions around the opening. The boreholes will be viewed

with a borescope, and the fracture patterns within the first 2 m on either

side of the opening will be mapped. Attempts will be made to estimate the

limits of the blast-damaged region.

-28-

Figure 5. Concept for concrete inserts

Obviously there will be differences in the profiles for each of the

holes, and one of the analyses will be to establish the extent of variability

among the holes. These results should serve as a guide for designing similar

measurements in the Exploratory Shaft.

2. Drift Monitoring. Measurements from MPBXs, BSMs, and RBLCs, would

continue for at least 3 mo after the last instrument is installed.

Measurements will be factored into numerical model and drift stability

analyses.

3. umerical Model Evaluations. Models are to be prepared to predict

rock mass responses for the WTM. Different two-dimensional models-will be

used for different purposes. Preliminary design 2-D modeling has been

completed using the elastic continuum assumption. A linear modulus of

deformation was used. This model has been used so that instrumentation

sensitivity requirements can be defined. A jointed rock model will be used

for model evaluations.

During the excavations of the room, the fractures will be capped. Results

will be made available for one of two 2-D jointed rock models that will be

used for further evaluations. f the mapping hows that the jointing is

irregular in orientation and continuity, then a jointed rock model using a

statistical description of the joints in a continuum will be used. 2 1 If the

mapping shows that the fractures can be represented with up to three ortho-

gonal joint ets with fixed orientations, then a more elaborate model will be

22used. This model contains five parameters describing joint shear

-30-

properties. The evaluations will be directed toward finding the best model

that is available to describe the rock mass.

Next, the measured deformations will be compared with the predicted values

and an error analysis initiated. Considerations will be given for use with

the direct and inverse methods. Comparisons of results of numerical

calculations and field measurements usually result in differences. Two

methods are popular in resolving these differences: the inverse method and

the direct method. The inverse method consists of rearranging the governing

equations so that some desired parameter, such as specific material

properties, appears as a set of unknowns. Since the final ystem of

displacements consists of more measurements than are required for the

calculations, optimization techniques are employed to solve for the selected

unknowns. In the direct method, the model is set up so that the calculated

quantities, .e., displacements, are the unknowns, and trial values for

various parameters are input into the equations to reduce the error between

the calculated and measured values. The direct approach lends itself better

to nonlinear analyses but may consume considerably more computer time with

resulting higher costs and possibly evaluation time delays. It i not clear

which method should be used for welded tuff, but evaluations in G-Tunnel

provide researchers with the opportunity to determine the best method to

resolve future differences. Furthermore, the procedures for the model

validation exercise in Yucca Mountain will be developed in this effort.

The focus will be on reducing the apparent discrepancies and assessing

whether the resulting differences are due to model limitations, parameter

definitions, stratigraphic variations, or measurement limitations and/or

-31-

errors. The final output of this exercise will be a best-fit comparison of

the field and predicted with explanations for resulting differences.

Recommendations will be made for improvements in planned model validation

efforts.

4. Other Testing. It is planned that a plate-loading test will be

performed in the demonstration room. The test will be performed with

procedures recommended by the ISRM. Details are not included in this test

plan.

D. Instrumentation - Continuous Recording

Table provides a listing of the planned instrumentation. The

instrumentation is divided into categories of continuous and discrete

measurements; the former category refers to instrumentation connected to the

data acquisition system (DAS).

1. ultipoint Borehole Extensometer. Four MPBX configurations are to be

used. The first, referred to as Type A, is an IRAD Model 4500, six-point

borehole extensometer. The unit has Invar rods and groutable anchors. The

unit is designed so that rod travel can be measured with a depth micrometer or

a sonic probe. It is planned that the depth micrometer will be used during

the mining phase, and this implies discrete measurements. After the deforma-

tions have stabilized behind the advancing face, the sonic probe will be

installed for continuous monitoring.

The operation of the sonic probe is based on measuring the time interval

required for a stress wave to travel between two or more points in a tube of

-32-

Table 1. Instrumentation Listing

magnetostrictive material contained within the probe. The time interval

measurement is converted to a displacement with a sensitivity to ±0.025 m.

Measurement ranges can exceed 0.3 . The unit is designed for remote signal

readout for distances up to 183 m in environments with high electrical noise.

The type A MPBXs are designed for manual measurements using a special readout

box provided by IRAD. We are modifying the data acquisition concept for this

testing. The readout box is connected to a specially designed switching unit

controlled by the computer. When data are to be taken, the computer activates

the switch box, which in turn causes the IRAD readout box to enter the reading

for each channel nto the data logger. Thus, the IRAD ystem monitoring is

the same as the other types of MPBXs.

A Type B MPBX is a GeoKon Model A-3, six-point borehole extensometer. The

unit is designed for routable anchors and contains Invar rod. The sensing

unit is a linear potentiometer with a measurement range of 10 cm and a

sensitivity to 0.025 m.

The Type C MPBX is a Terrametrics Model 293-6CSLTCR1, six-point

extensometer with routable anchors. The rods are made of Invar. The sensing

unit is a DC-LVDT with a 10-cm measurement range and a sensitivity to

±0.025 mm.

The Type D MPBX is a Terrametrics Model CSLT-4, four-point extensometer

with groutable anchors. The other details are similar to the Type C units.

2. Rock Bolt Load Cells. Rock bolt load cells selected are Terrametrics.

Model PC-60, steel units. The units have a capacity of 535 KN with a

sensitivity to 267 . The units are fabricated with strain gages as the

sensing elements. They are to be attached using manufacuturer-supplied

installation procedures to 22-mm-diameter mild steel rock bolts that have

epoxy anchors.

3. Borehole Stressmeters. The borehole stressmeter selected is an

SNL-developed unit. The unit is the rigid inclusion type with a strain

gage sensor. The stressmeters are to be installed into AQ-size boreholes with

specially fabricated wedges. Subsequent rock mass unloading compresses the

wedges, and borehole stress changes are determined from data processing of the

strain gage voltage changes. The BSM has a sensitivity of 130 Pa.

E. Instrumentation - Discrete Measurements

1. Permeability. Test equipment and instrumentation for fracture

permeability testing are not standard. The principal equipment used downhole

consists of a pair of straddle packers suitable for use in NQ-size holes. The

straddle packers are connected by a short perforated pipe so that a

pressurized length of approximately 0.5 m is available. The packers are to be

inflated with nitrogen to a pressure less than 2.4 WPa. The packer is

connected to a flowmeter and pressure gage with pressure pipes. The

flowmeter, manufactured by Flow Technology, has a water flow range up to

The sensitivity of the flow meter is to be within

-35-

The pressure gage, manufactured by Kulite, has a range up to 1.4 MPa The

pump, manufactured by Robbins and Myers, Inc., is rated up to

6 x Flow rates and injection pressures are regulated with

valves. easurements are to be taken under steady-state flow conditions at

each of five pressure-flow rate steps. The steps will consist of five flow

rate measurements, nominally at pressures of 0.3, 0.6, 0.9, 0.6, and 0.3 MPa.

If flow rates are high, the pressure range is reduced because of equipment

limitations.

2. Borehole Deflectometer. The borehole deflectometer, Terrametrics

Model PBD/TCD, operates on the principle that a sensor i traversed along a

continuous tubing in the rock mass and an angle change record is made. The

sensor consists of two straight fixed-length segments linked together with a

strain-gage-based flexible connection. During a traverse, the flexible

connection transmits a continuous signal that is the analog of the deflection

angle between the two segments. The measurement principle is to traverse the

boreholes before, during, and after the mining operations so that the

cumulative angle distortion of the rock mass can be followed. In essence, an

angle change profile is established.

Angle change measurements can be summed to provide displacements at

selected points in the rock mass for each traverse. Comparisons of calculated

displacements for mining stages provide an indication of the effects of

excavation on the surrounding rock mass.

-36-

An essential facet of borehole deflectometer measurements is to ensure

that the traverse path accurately reflects the rock mass movements. This is

accomplished by inserting a special PVC tubing into each of the measurement

boreholes. This tubing has four grooves that guide the deflectometer and form

a permanent reference track that follows the small rock mass displacements.

3. Rod Extensometer. The rod etensometer is a hand-operated device used

to measure drift convergence. The unit is manufactured by IRAD Model RFR,

and uses a sonic probe as the sensing unit. The sonic probe has a sensitivity

of 0.025 mm. The rod extensometer is formed by precise length segments and

has a measurement range of 0.6 m. The rod extensometer is designed to be

removable. The sonic probe can be read remotely.

Special anchors are to be fabricated on MPBX heads so that cross-drift

measurements, both vertical and horizontal, can be made at periodic ntervals

during the mining.

4. Hydraulic Pressure Cells. Terrametrics/Glotzl Concrete Stress Cells,

Model 10/20, are to be inserted in the concrete inserts. The principle of

operation involves a sensing system, located in the pressure cell, that is

isolated from the measurement system, which is connected to a hydraulic pump.

The closed sensing system monitors the stress surrounding the pressure cell

and converts this stress to hydraulic pressure on the cell. When a

stress/pressure measurement is desired, a Terrametrics Model MlB16 pump is

actuated and pressure in the measurement system is increased. A special

bypass valve in the cell shifts the direction of flow so that the pressure

-37-

A

does not increase. At the attainment of this maxium pressure in the

measurement system, the flow rate is reduced and a diaphragm in the tell

closes at a pressure very near the pressure in the sensing system; thus, the

stress is determined. The pressure cell can record stresses up to 30 MPa with

a reported accuracy of

A factor in the use of hydraulic pressure cells it the hydraulic head

caused by the fluid in the tubing connecting the pressure manifold and the

pressure cells. Since the measurement objective is to record the changes in

stress after the cell is in place, then the initial measurement at the time of

installation includes the line hydraulic effects and further changes are

attributed to stress behavior.

F. Data Acquisition System

1. Continuous. Data acquisition is designed around the HP 9845 desktop

computer. Figure 6 shows that the DAS is located in two facilities in and

around G-Tunnel. The underground portion is located in a room

excavated at the top of the Rock Mechanics Drift (Figure 1). Temperature is

maintained at 20 and the relative humidity can be maintained at

The companion room for the DAS is located in the -Tunnel bunker near the

tunnel portal, and can be accessed on a 24-hr basis should conditions

warrant. The system is designed to allow control from either the

instrumentation alcove or the bunker. This control includes making program

changes and evaluating data that has been collected.

-38-

figure 6. GTUP Data Acquisition System-39-

The DAS is to be operated continuously over the duration of the

evaluations, tarting with the premining phase.

2. Discrete. Data for discrete measurements are recorded on special

forms reated for the pecific measurements. These completed forms become

part of the data record for the evaluations. Data are obtained on pecific

data recorders or readout devices for each of the measurements.

a. Permeability. Data for these measurements consist of test date,

water temperature, location of test interval, size of measurement

interval, injection pressure, flow rate, time interval for flow,

and fracture descriptions. The latter are obtained from core logs

and/or borescope investigations.

b. Borehole Deflectometer. The output for the borehole deflectometer

is a continuous electrical signal that is the analog of the

deflection angle between the two fixed length segments. The

traverse will be sampled at intervals of not more than 0.2 m and

data recorded to provide a continuous record of the traverse

displacement normal to the borehole. The data collected will

consist of traverse record, borehole used, test date, and

equipment used.

c. Rod Extensometer. The IRAD Model MB-7 Sonic Probe Readout Box

provides a digital display for sonic probe sensors and can be

placed up to 183 m from the sonic probe without loss of accuracy.

The data collected from rod ext extensometer measurements will consist

of date, measurement location, number of segments in rod,

temperature, identification of rod segments, serial number of

readout box, and digital readout value.

d. Hydraulic Pressure Cell. The hydraulic pressure cells are

connected to a manifold at the measurement station with pressure

tubing. The manifold contains a valve arrangement so that

pressure readings to individual cells can be controlled. The

manifold is connected to the Terrametrics Model M1B16 electric

motor-driven pimp. The pump has an automatic flow rate regu-

lator. The procedure is to pump oil into the system at a slow,

timed rate. When cell bypass occurs, very slow pumping, at a

delivery rate of less than 0.5 cm m, continues until there is

no further increase in pressure. Normally, a pressure measurement

takes 5 min. This pressure is then related to the stress on the

hydraulic pressure cell. Data recorded are HPC identification and

location, temperatures at tell and manifold, maximum pump

pressure, and test date.

G. Instrumentation Calibration

Calibration of instruments and sensors falls into three categories:

standards, fixture-dependent, and field. The first category refers to

subjecting measurement sensors to calibration checks in the SNL calibration

41-

lab. Items to be included are linear potentiometers and DC-LVDTs from the

MPBXs; flowmeter and pressure gage for fracture permeability apparatus; the

pressure pump for the HPCs; and all length calibration gages. These units are

to be calibrated in SL-approved calibration laboratories.

The second category refers to those efforts where a calibration device or

fixture has to be fabricated to ensure that the expected measurement is

accurate. Output from the sonic probe, used in MPBX and rod extensometer

measurements, must be calibrated in a special fixture to ensure accuracy with

the entire measurement system. This is accomplished by placing the probe in a

fixture so that the sensing unit can be displaced a known amount and the

readout quantity verified.

The borehole deflectometer is to be attached to a special rig so that the

movement of one rigid segment can be accurately related to the other and

electrical output is to be correlated with actual physical displacements of

the segments to ensure measurement accuracy.

For example, rock bolt load cells are to be placed in special fixtures

that can be placed in an SL universal testing machine. Electrical output

from RBLCs is to be correlated with actual force measurements. The

electronics arrangement is to duplicate the data system used in the field.

The borehole stressmeter requires a block of welded tuff that can be cut

into a 15-cm cube. The cube is to be cored with an AQ-size diamond bit so

that the hole is centered in two parallel faces. The probe is to be inserted

-42-

in the hole and the entire assembly placed in a universal testing machine.

The output from the sensor is to be correlated with the actual forces and

converted stresses that result.

The final fixture that has to be fabricated is for the borehole

permeability straddle packer unit. The basic fixture consists of a pipe

having the same inside diameter as the borehole. The pipe is to have a

perforated bypass interval that contains a pressure regulator. The water can

flow through the bypass valve into a measuring tank. First, the straddle

packer unit is to be inserted in the pipe away from the perforated region and

the packers inflated to the design pressure. Water is to be pumped into the

measurement interval so that the effective volume between the packers can be

measured. Next, the straddle packer unit is to be placed at the bypass point

and the packers reinflated. Pressure-flow rate measurements are to be run so

that the hydraulic features of the piping can be factored into data

reductions. The principal factor needed is the pressure loss between the

pressure gage located on the surface and the actual pressure at the injection

interval.

Field calibrations (third category) apply to the MPBXs that have linear

potentiometers and DC-LVDTs. These instruments have built-in devices where

the sensing units can be accurately displaced and the entire data system

output checked for accuracy.

H. Laboratory Tests

Table 2 lists the laboratory tests to be performed on core samples. In

addition, cores will be inspected by geologists and standard logs recorded.

-43-

Table 2

Laboratory Tests

IV. EXPERIMENT MANAGEMENT

A. Responsible Personnel

The following SL personnel have major responsibilities in this experiment:

Roger E. Zimmerman, Principal Investigator

Program Supervisor

Contract Supervisor

Modeling Supervisor

Test Engineer

Robert L. Schuch

Field Coordinator

Joe Bradshaw

Instrumentation and Data System Installation

Prepare and conduct Permeability Measurements

B. Schedule

Figure 7 is a PERT Chart listing the main activities associated with this

evaluation. Relationships with NNWSI milestones are shown.

C. Documentation

The details associated with the planning of this effort are covered in

this Test Plan. A final SAND report, a Level 2 NNWSI milestone, is to be

written on the results of the measurements (Figure 7). Special evaluations

pertinent to Exploratory Shaft testing will be reported as SNL Keystone

documents. It is expected that there will be a number of papers submitted to

technical and professional proceedings and journals covering various aspects

of the evaluations as they unfold.

-45-

Figure 7. Mining Evaluation Planning Schedule

D. Quality Assurance (QA)

The mining evaluation in G-Tunnel is implemented under the SNL

Organization 6000 QA Program Plan and is designated as a quality Level 3

effort (per QP II-1). Q records for the overall effort hall consist, at a

minimum of the Test Plan; interim, topical, and final reports; and any peer

review documentation. Decision-making telecon notes, conference notes, and

trip reports, along with QA audits or surveys, shall be kept in the project

working file. QA documents located in the project working file shall have

copies placed in the NNWSI Central File.

Details associated with record keeping are:

1. Test Plan. The Test Plan is kept in SNL and SAI project offices and

in the Instrumentation Alcove of the TUF.

This Test Plan is a SNL Keystone Document and distribution of copies

follows those procedures. As a minimum the completed Test Plan will be

distributed to:

-47-

.

After distribution, the copy kept in the Instrumentation Alcove in

G-Tunnel will be the master copy. Any changes to the plan will be made in

writing for approval by the principal investigator, division supervisor, and

QA coordinator. Approved changes will be kept with the master copy and copies

distributed to appropriate personnel.

2. Logbook. A DAS logbook is kept with the operating computer. Entries

pertinent to the daily operations of the project are recorded here. The DAS

logbook shall be maintained in accordance with EPI-II-5.

3. Source Program, Data Files, and DAS Calibration Records. he source

program is prepared in Albuquerque and stored on the computer there. A copy

is placed on the computer in the GTUF in two forms. One copy is recorded on

the hard disk, and the other is stored on the autostart cassette. The

autostart program overrides any unauthorized change in the program at the

G-Tunnel computer. Any changes in the program are coordinated with the data

system programmer in Albuquerque and logged into the logbook in GTUF. As

appropriate, new autostart cassettes are prepared in Albuquerque and

transported to G-Tunnel for use. At the conclusion of testing, the source

program is entered onto a tape cassette for permanent storage. This tape

cassette becomes part of the NNWSICF.

All data are initially stored in the two hard disk units in the GUF.

Data are stored in raw and converted data files. Periodically, tape cassettes

are made for all data stored in either of the files and these are transported

to Albuquerque for data processing. These tapes are kept in temporary storage

in Albuquerque and later, all raw and converted data are transferred to the

permanent QA data tape cassette.

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DAS calibration records re kept on floppy disks at the GTUF. They are

updated as needed, and the new record becomes part of the regular data file.

Therefore, there is a continual record of calibration changes for all computer

constraints. Sensor calibration plans have been discussed in the

instrumentation section. These calibration records are to be assembled and

entered into the regular data file for the WTM evaluations.

4. Contractor Records. Field support contractors will have an approved

QA file under the contract obligations. Pertinent records are to be

transferred to SNL for permanent QA storage. These records include:

(1) contractors will provide a record of details pertaining to the

installation procedures and wiring of each of the instruments installed;

(2) contractors will provide records of sensor and instrumentation

calibrations; and (3) contractors will provide a record of activities

pertaining to any troubleshooting required for instruments. The problems will

be identified and solutions described.

5. Nonconformance Actions. In accordance with Quality Level 3,

provisions any nonconformance reporting shall consist of identification of the

nonconformance, the disposition, and the corrective action taken. These

details will be entered into the WTM logbook.

E. Safety

Existing DOE Manual Chapters and NTS Service Organization Standard

Operating Procedures will be applied to appropriate efforts.

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V. EXPERIMENT EVALUATIONS

A. Objectives

The first objective for the mining evaluation is to review relevance of

standard rock mass rating techniques for use in defining stabilization

procedures for a repository-sized room in welded tuff.

The two rock mass rating systems have been briefly defined and referenced,

i.e., CSIR and Q-system. The WTM will provide for a detailed

application of these ratings for the purpose of developing a more accurate

predictive model for welded tuff. feature in the study is the application

of these ratings to a cross-section shape that has not been previously

constructed in welded tuff. The 6.1-m span is relatively large, and

preliminary designs indicate that it can be stabilized with the standard rock

bolts and wire mesh techniques commonly used on the NTS. If unstable

conditions exist, either the drift convergence rates could be excessive (10.01

mm/day) or roof displacements could exceed 10mm ; then, rock bolt yield

strengths could become important. The latter is highly unlikely in the time

period under consideration in this evaluation. The rate effect is important

for analyzing drift stability predictive models related to the rock mass

rating systems.

The second objective is to apply control blasting techniques in

construction of a room in welded tuff for subsequent evaluations and

recommendations for Exploratory Shaft efforts."

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There are NNWSI requirements to develop techniques to control blasting and

minimize blast damage in welded tuffs. This has never been seriously

attempted in this particular medium. Part of the evaluation consists of the

standard visual mining evaluations associated with drilling and blasting.

These evaluations include time and motion studies required to accomplish the

mining tasks. Also, measurements are made of the volume of rock excavated and

the resulting cross-section size that is excavated. Part of the evaluation

consists of a visual inspection and subjective evaluation of the blasting

effects. These methods alone do not quantify and ensure the minimization of

blast damage and the potential effects on creating preferential pathways for

water migration. Thus, the permeability testing is added.

The permeability testing consists of the recording of permeability

profiles before and after the blasting and relating the results to the known

mining practices used. The permeability profiles are to be taken at three

stations along the room, and different mining drilling patterns and blast

techniques will have been used to enhance the evaluations. Emphasis will be

on taking measurements within 2 of the freshly exposed urfaces. An

integral part of the evaluation will be the logging of the fractures in these

intervals before and after blasting so that the permeability measurements can

be analyzed better. Hydraulic quotients will be calculated for these

intervals to determine the changes caused by blasting and drift urface

relaxation phenomena. An output of the evaluations will be a recommendation

as to the best of the mining methods to minimize blast damage.

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The third objective, measure and evaluate drift convergence phenomena for

purposes of determining the responses of the welded tuff to mining," applies

to the period of drift convergence prior to the placement of the rock bolts.

The measurement techniques will be the same for the periods before and after

rock bolting, but evaluations will be for different purposes. The emphasis in

this objective is to design, perform, and evaluate measurement techniques

during the mining phase so that possible measurement stability problems

associated with blasting or muck removal can be ascertained. The measurements

before and after the rock bolting support the Objective evaluations.

There is always some drift convergence at the mining face due to the

removal of the material preceding the face. In order to measure drift

convergence during remaining mining operations, instrumentation has to be

placed as lose to the face as possible so that the remainder of the

convergence an be measured. This means that timing and sequencing of

measurements is essential. This also means that the instrumentation ust be

placed close to the face and must remain electronically stable and unaffected

by the blasting. Successful measurements will require that the MPBX heads be

installed so that they are protected. Measurements taken before and after

the blasts will provide the necessary documentation. In the event that one or

more units is damaged, then procedures will be implemented to reinstall the

measurement station. A result of the evaluations will be recomendations for

performing the measurements successfully in the Exploratory Shaft.

The actual measurements will be related to elastic theories and the

results of the numerical calculations in the next objective.

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The fourth objective, perform 2-D numerical model caculations of the

repository-sized room and compare results with the measurements in objective

(3) to determine reasons for any differences," relates to comparisons of field

deformation measurements (MPBX and rod extensometer) with predicted values.

Incorporated in the evaluations will be field-mapping of the joints so that

they can be best represented in the models. One model uses statistical

descriptions of oints, and the other requires that joint sets have

parallel joints but includes a more sophisticated joint shear model. The

first evaluation will be to assess which model has more promise for repre-

senting the joints. The next evaluation will be to assess whether the direct

or inverse method will provide the best results. The inverse method will

be tried first because it has potential for being the most economical. If

this is not found satisfactory, then the direct approach will be tried. The

expected outcome s that the model experiment measurements can be brought to a

minimum variation. If differences greater than 20 percent exist, then

recomendations will be made as to possible:

1. improvements for models,

2. improvements for measurements, and

3. improvements of defining material properties.

The fifth objective is to "evaluate instrumentation installation

techniques and resulting measurement results to improve measurement

capabilities."

Deformation measurements efforts pertinent to Objective A relate to those

techniques that apply during the mining period. This objective focuses on the

instrumentation performances over a relatively short period of time. Sensors

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are to be connected to the DAS, which requires the more elaborate calibration

procedures. An activity within this objective will be an evaluation of the

adequacies of the calibration techniques, and recommendations for improvements

will be made as necessary. Instrumentation performance will be focused on how

the sensor performed in relation to how it was expected to perform. Reasons

for descrepancies will be offered and residual testing will be scheduled as

necessary to ensure that the problems are defined properly.

The use of the borehole stressmeter is new in this application, and there

is need to determine whether placement techniques are adequate and measure

ments reasonable. It is not expected that the BSM will provide data that can

be hecked accurately with the numerical calculations because stress measure-

ments are highly dependent upon localized conditions in the urrounding

rock. 2 4 It is hoped that the measurements will reflect meaningful trends

and evaluations will be used to provide expected ranges for measurements in

the Exploratory Shaft. Instrumentation durability will also be assessed.

The use of the borehole deflectometer will be a first in welded tuff and

for this pre- and postmining application, and measurements results are

somewhat uncertain. Comparisons of results with the numerical models will

provide indications as to the accuracies. An expected recommendation is a

statement as to whether use of the borehole deflectometer is feasible in hard

rock, and if o, what procedures should be used for uccessful use in the

future.

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The emphasis in the application of the HPCs is to evaluate the

installation and formability considerations. The HPCs will be monitored for a

30 day period to establish degree of uniformity in similar measurements and

then we will extract them from the concrete inserts to assess the conditions

of the HPCs Output from this effort will be a recommendation for future use

of these cells.

The sixth objective, "serve as a test facility for supplemental rock

mechanics testing (i.e., plate-loading testing, possible demonstration of

horizontal boring machine)," does-not require an evaluation. The intent is to

provide a facility with a DAS that can be used to monitor rock mass changes

caused by other activities. The only evaluation expected is whether the

measurement systems responded to what was expected and, if not, why.

B. Expected Results

The purpose of the mining evaluation activities is to conduct an

evaluation of rock welded tuff behavior caused by the excavation of a

relatively short room. Included with the excavation are a number of

measurements designed to quantify the overall rock behavior. It is expected

that evaluations will:

1. demonstrate technical feasibility of construction of this sized room

in welded tuff,

2. result in recommendations for instrumentation and measurement

techniques for Exploratory Shaft testing,

3. serve as a reference for future experiment/model evaluations for

welded tuff,

4. enhance drift stability predictive models, and

5. quantify blast damage effects in welded tuff.

VI. REFERENCES

1. Nevada Nuclear Waste Storage Investigations NVO-196-13. FY 1980 ProjectPlan and FY 1981 Forecast, Las Vegas, NV February 1980.

2. Preliminary Design and Definition of Field Experiments for Tuff RockMechanics Program; R. . Zimmerman SAND81-1972, Sandia NationalLaboratories, Albuquerque, NM. June 1982.

3. Conceptual Design of Field Experiments for Tuff Rock Mechanics Program; byR. . Zimmerman SAND81-1768, Sandia National Laboratories,Albuquerque, NM. October 1982.

4. Evaluation of Tuff as a Medium for Nuclear Waste Repository. Interim

Status Report on the Proerties of Tuff; by J. . Johnstone and K.Wolfsberg, eds., SAND80-1464, Sandia National Laboratories,Albuquerque, NM. July 980.

5. Site Exploration for Rock-Mechanics Field Tests in the Grouse CanyonMember, Belted Range Tuff, U 12g Tunnel Complex, Nevada Test Site; byB. S. Langkopf and E. Eshom. SAND81-1897, Sandia NationalLaboratories, Albuquerque, NM February 1982.

6. Geomechanics Classification of Rock Masses and its Application inTunneling," Z. T. Bieniawski, Proc. 3rd International Congress onRock Mechanics, ISRM Denver, C., 1974.

7. "Estimation of Support Requirements for Underground Excavations,"H. Barton, R. Lien, and J. Lunde Proceedings 16th Symposium on RockMechanics, U. Minn., 1977.

8. NNWSI Issue Hierarchy. Site Characterization Plan. In prep.

9. Nuclear Regulatory Commission, 10 CFR Part 60.. Disposal of High-levelRadioactive Wastes in Geologic Repositories: Technical Criteria.June 21, 1983.

10. Application of the Q-System in Design Decisions Concerning Dimensionand Appropriate Support for Underground Installations." . BartonF. Loset, R. Lien, and J. Lunde, Subsurface Space, . Bergman, ed.,Vol. 2.

11. "Geotechnical Field Measurements, G-Tunnel, evada Test Site," R. .Zimmerman and . C. Vollendorf. SAND81-1971, Sandia NationalLaboratories, Albuquerque, NM May 1982.

12. Monitoring the Behavior of Rock Tunnels During Construction, Z. T.Bieniawski and R. K. Maschek. The Civil Engineer in South Africa,Vol. 17, No. 9., 1975.

13. Measurement of Displacements in Tunnels, E. J. Cording. Proc. 2ndCongress IAEG Braz Assoc. Engng. Geol., Sao Paulo.

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14. "Some Aspects of "Characterization' Problems in Geomechanics,"A. Cividini, L. Jurina, and G. Gioda. Int. J. Rock Mech. Min. S. &Geomech. bstr., Vol. 1, 1981.

15. Rock Testing Handbook, RTH 381-80 (U.S. Corps of Engineers, 1980)

16. "Analysis of Steady-State Hydraulic Tests in Fractured Rock," D. P.Hodgkinson, AERE-R 11287, DOE/RW/84.076, United Kingdom Atomic EnergyAuthority. Oxfordshire, U, July 1984.

17. Instrumentation and Evaluation of the 5191 oot Level of the SilverShaft, Mullan, Idaho," by . Barton, K. Bakhtar . Khodarerdian S.

Woodhead and D. Joss. TR 82-53-Terra Tek Report. July 1982.

18. "Rock Characterization Testing and Monitoring, ISRM Suggested Methods,"E. T. Brown, editor, Pergamon Press, 1981.

19. "Rock mass Classification of Candidate Repository Units at Yucca MountainNye County, Nevada," B. S. Langkopf and P. F. Gnirk, SAND82-2034,Sandia ational Laboratories. Albuquerque, NM. In prep.

20 "The Effect of Variations in the Geologic Data Base on Mining at YuccaMountain for NNWSI Dravo Engineers, Inc. SAND84-7125, SandiaNational Laboratories. Albuquerque, NM.

21. "A Material Constitutive Model for Jointed Rock Mass Behavior," by R K.Thomas. SAND80-1418, Sandia National Laboratories. Albuquerque, NM.

22. "Analysis of tripa Full-Scale Heater Test," D. E. Maxwell and B. W.Dial, SAI-FR-221-1, Science Applications, Inc. San Leandro, CL.September 1981.

23. "Borehole Inclusion Stressmeter Measurements in Bedded Salt," by C. .Cook and E. S. Ames. Proceedings 2th Symposium on Rock MechanicsAustin, TX 1979

24. "Back Analysis of Measured Displacements of Tunnels," by S. Sakarai andK. Takeuchi, Rock Mechanics and Rock Engineering, Vol. 16, o. 3,

August 1983.

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