ML20151C925
| ML20151C925 | |
| Person / Time | |
|---|---|
| Issue date: | 07/12/1988 |
| From: | Prestholt P NRC |
| To: | Linehan J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| REF-WM-11 HLWR, NUDOCS 8807220252 | |
| Download: ML20151C925 (293) | |
Text
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~[ - k, UNITED STATES
[ g NUCLEAR REGULATORY COMMISSION E
-G WASHINGTON, D. C. 20555 s.,.....j Reply to:
1050 East Flamingo Road Suite 319 Las Vegas. Nevada 89119 (Tel: (702) 388-6125 FTS: 598-6125 MEMORANDUM DATE: July 12, 1988 FOR: John J. Linehan, Acting Chief, Operations Branch Divi sion of High-Level Waste Management FROM: Paul T. Prestholt, Sr. OR - NNWSI
SUBJECT:
NNWSI Si te Report for the month of June, 1988
- 1. DUGLIIY GSSURGNCE A. Concerning the June NNWSI DA audit of the USGS in Denver, Dr. Larry Hayes, USGS Technical Project Officer (TPO) is chall enging a number of the Standard Deficiency Reports (SDRs) that were issued by the auc4i t team. Al so. Dr. Hayes is chal1 enging al1 of the severity 1evel 1 (most severe) SDRs.
The audi t team's report has not been i ssued. Mr. Carl Gertz, WMPO Program Manager, has indicated that no deci sion on 8807220252 880712
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dw3/ disk 12/071588.rpt/Linehan/LV the audit team's recommendations will be made until the team's report is finalized. B. Half of the agenda for the June Project Manager-TPO nieeti ng concerned DA. Three topics were discussed: I. Qualification of the Quality Assurance Program II. A discussion of the audit process as presently used by the NNWSI; III. The revision of the NNWSI DAPPs to match the 88-9 document. The 88-9 is the new de*lignation for the NNWSI Quality Assurance Program Plan. I. The definition of a "Qualified Quality Assurance Program" is still evolving. However, the target date for achievement is January 1, 1989. The following process for the implementation of a fully qualified QA program was presented (from the attached handout) 185K SUMM88Y gE E8gcggs Project l evel plans Process defined by SAIC l Qualification-Certification Process defined in WMPO QAPP (88-9 of personnel document) l' I Training Process to be finalized by Training Management Plan, implementing procedures, and letter of di recti on from WMPO. Technical /OA prerequisites Definition and categorization (new, ongoing) of activi ties to be 2
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- dw3/di sk 12/071589. rpt /Li nehan /LV defined from SCP networks by SAIC.
List and catalog of OA technical prerequisites to be prepared by. SAIC with input from participants. including four sample networks develsped for DOE Hg. review. Prioritization of remaining networks to be established for those beyond the four examples. Networks will be created for each activi ty showing prerequisites and schedules. Readiness Review WMPO may conduct readiness (option) r evi ew ( s) to determine whether proj ect is prepared to implement procedures. The following issues are being actively addressed: Integration of project and DOE Hg. efforts, e.g., What will be provided to NRC and when? What level of detail should be on networks? How will DOE Hg. and project QA documents be made to conform with each other? Defini ti on of resources required to complete all actions on time. Definition of processes and allowed time periods for document preparation, review, and approval. Priority of this activity vs other high priority activities (SCP, ESF). 3
dw3/ disk 12/07158G.rpt/Linehan/LV A schedule f or meeting the requirements to implement a fully qualified DA program is included in the handout. II. The NNWSI QA program defines an audit as: "A planned and documented activity perf ormed to determine by investigation, examination, or evaluation of objective evidence the adequacy of and compliance with
- establ i shed- procedures
- codes and standards
- instructions and drawings
- other applicable requirements as well as the effectiveness of implementation."
The enclosed handout discusses:
- audit preparation
- the audit cycle
- audit performance
- audit reporting
- audit follow-up
- an example of a WMPO SDR
- the draft procedure review checklist III. The enclosed handout presents the schedule for the revision of the participants OAPPs to match the 88-9 document. The process started with the transmission of the 88-9 document to the participants on May 25, 1988, and ends (as far as WMPO is concerned) with the transmi ssi on of the WMPO revis ed participant DAPPs to DCRWM for review / approval on August 7, 1988.
II. GEQLQG'f A. On June 7, I attended the Sample Overview Committee (SOC) meeting at the new Sample Management Facility (SM!:) in area 25, Nevada Test Site. The meeting included a tour of the new facility. The SMF is housed in two buildings. One building houses the offices, sampl e preparation rooms, sample viewing room 4
a dw3/ disk 12/071588.rpt/Linehan/LV ., and storage. The second building will be used for storage. The ) set-up i s very impressive. j The transfer of core from the USGS Mercury (NTS) facility to the SMF-is continuing. Thi s acti vi ty ir expected to be completed by the end of the calendar year. The procedures for the operation of the SMF have been written and are under review by the QA organization. It is not expected that the SMF will be open for business before September and it is more likely that it will be October or November. Enclosed is a copy of the charter for the SOC and AD-SOC-1.
"Aoproval Procedure of Request for NNWSI Project Geologic Samples." These documents are in draft, they are not finalized and are submitted only to show the direction the NNWSI project is going.
B. The problem of qualifying the core (samples) f ro.a the boreholes drilled to date for DA level 1 activites is continuing to get pri ori ty attention. WMPO sent a letter to each participant asking that they indicate which samples in their possessi on (borehol e number and depth) were essential to DA level 1 acti vi ti es. The answers to that letter are enclosed. The positions of the participants on the need to qualify existing samples is summarized in a document titled "Need for the Qualification of Existing Drillhole Samples." Because of the importance of this problem, I'm reproducing the total document: NEED FOR THE QUALIFICATION OF EXISTING DRILLHOLE SAMPLES POSITIONS OF THE PARTICIPATING ORGANIZATIONS ON THE IDENTIFICATION OF EXISTING NNWSI PROJECT DRILLHOLE SAMPLES THAT MAY BE USED TO SUPPORT LICENSING DOCUMENTS: RESPONSES TO A LETTER (DTD. 5/2/88) FROM C. GERTZ-WMPO/PM TO THE TPOS U.S. GEOLOGICAL SURVEY: IOltial Resaggge 5
dw3/ disk 12/071589.rpt/Linehan/LV "Virtually all of the existing core and bit cuttings were used in the preparation of lithologic logs which were published or will be published in drillhole basic data reports. ~ These data reports, in turn, have been and will continue to be used and referenced in our interpretative reports, position papers, and NNWSI Project licensing documents. We cannot determine that any speci fic sample will or uill not play a part in the licensing process. In fact, every oxisting sample is susceptible for sel ecti on as the basis for some scientific interpretation, analysis or conclusion that can be used in support of, or against, licensing. Therefore unless you intend to exclude all USGS drillhole basic data reports f rom the licensing process, all drillhole samples, including core, cuttings and water from either the saturated zone or extracted from rocks of the unsaturated zone, should be considered as candidates for qualification". Bevined Bese90se "The two major stratigraphic intervals thus wo :. ave sel ected are the Topopah Spring Member of the Painth ,o luff and the tuffaceous beds of Calico Hills. The s. '.erval s include the host rock and the potential barrier between the repository and the water table, respecti vel y. Characterizatior, of samples from these intervals are considered a high priorit, . Other considerations are intervals that include contar.ts between subjacent stratigraphic units, which help establish the primary geometric configuration of the repository area.
"We have included only continuously cored holes in this selection process. Although all holes where geophysical iogs and bit-cutting samples have been collected represent an integral subset of data for establishing the geologic framework of Yucca Mountain, continuously cored holes have provided the fundamental reference data set, fecm which reliable lithologic and geophysi cal correlations are made.
"Coreholes that penetrate the above mentioned stratigraphic units within or near the area enclosed by the perimeter drift are presently considered more important for later use in licensing interactions and are given a higher priority."
LOS ALAMOS NATIONAL LABORATORY:
"Key intervals from specific cores can be identified for the alteration history and tracer evaluation studies. However, our work on the mineralogy of transport pathways and fracture mineralogy requires characterization of all units across the repository block and along potential ground water flowpaths to the accessible environment. To do,this, a complete three-di men si onal picture of the mineral distributions at Yucca Mountain must be constructed. We feel that use of limited subsets of existing data will not be adequate to document the many changes in mineralogy that occur vertically and laterally at Yucca Mountain."
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Attachment 1 (Enclosed) - Provides a list of boreholes, identification'of analysis completed, accuracy, and sensi tivity of sample depth and' location, and estimates cost and time to duplicate. tests.
' Attachment 3 (Enclosed) - Draft Report by Broxton, Byers, and Warren proposing and compiling inf ormation f or a possible peer review,of data from nine boreholes; six are the same as proposed by the-USGS.
SANDIA NATIONAL LABORATORIES:
"Existing' data and data from ongoing activities with ' unqualified core' may, as necessary, be used as supporting or corroborating inf ormation in the licensing process. Our plans for obtaining pri mary data require samples f rom new coreholes at Yucca Mountain and most of our requirements are for samples from locations that have not been previously cored. Therefore, we cannot identify a specific subset of existing core that, if qualified, would significant1y' change our requirements as expressed in the SCP.
If the pl anned drilling were greatl y reduced, the reduction might force us to attempt to use existing core for gathering future primary data. The nature of such reduction would dictate our specific qualifying requirements".
-LAWRENCE LIVERMORE NATIONAL LABORATORY:
,"Although we have received core or cuttings samples from various depth intervals in eight drillholes on or near Yucca Mountain and have used some of the material in experiments, none of these stapl es need be quali fied i f repository horizon samples become avai ~ able in a ti mel y manner. "
SUMMARY
OF POSITIONS: The positions range from:
- 1. All of the existing core / cuttings should be considered for qualif! cation because much of the data derived from drillhole samples (e.g., subsurface stratigraphy) has already been released i r: reports which will be referenced in licensing documents. This posi tion was subsequentl y modi fied to include only the major subset'or data f rom continuously cored holes penetrating the Topopah Spring Member of the Paintbrush Tuff and the Calico Hills tuffaceous beds. Coreholes within or near the perimeter drift are of most importance.
- 2. Perhaps none of it will need to be qualified. The latter position intends that new core will meet all of the Project requirements toward resolving licensing issues, but with the caveat that time contraints (e.g., the need to meet Project deadlines) or restrictions on drilling in the repository block (e.g., number of holes and/or depth of holes) might create a need for qualifying some drillhole samples.
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9-dw3/di nk 12/071588. rp t /Li neh an /LV ISSUES TO DE RESOLVED PRIOR TO THE RECOGNITION OF A SUBSET OF EXISTING CORE SAMFLES FOR QUALIFICATION
- 1. FINALIZATION OF THE DRILLING PROGRAM AT YUCCA MOUNTAIN: What restrictions on number of holes or their depth will be placed on the Project? For example, no drilling below the water table may mean that all core from the Crater Flat Tuff will have to be qualified. Does the present Drilling Pr ogram reflect the possibility that existing drillholes might not be part of the primary data set?
- 2. SCHEDULING IMPACT: What will be the impact on the present schedule if the existing data derived from drillhole samples can not be used as primary data and some tests and experiments must be duplicated? These experiments and the related core / cuttings samples would have to be identified. It has been suggested that delays up to five years (e.g., sorption experiments) may result.
PROCEDURES AND FACILITIES REQUIRED FOR A QUALIFICATION EFFORT
- 1. STATUS OF THE CORE TRANSFER: For any technical study of the actual drillhol e material preparatory to a qual i f i cati on effort the drillhole samples will have to be in storage at the Sample Management Facility (SMF). The transfer is in progress and core / cuttings from 16 holes has been moved to the SMF. The projected completion of this activi ty i s late 1988 to early 1989.
- 2. STATUS GF THE SAMPLE MANAGEMENT FACILITY: Thi s facility muut be operational prior to any work on the axisting material (e.g.,
relogging of selected intervals or the preparation of gamma logs from core). SMF technical procedures and administrative procedures are in formal review. Computer software $s being developed, however, the establishment of a 56 kilobit communications link f or the f ull operation of the SMF computer system and the software has not been resolved. The software will have to be reviewed and approved.
- 3. STATUS OF AP 5.90 QUALIFICATION OF DATA OR DATA INTERPRETATIONS (EXISTING DATA) NOT DEVELOPED UNDER THE NNWSI PROJECT DA PLAN: The AP i s under /ormal review. It is important to the qualification of exi sting .. ore because i t establi shes a cutoff date for NNWSI Proj ect prsduced exi sti ng data as being data generated before the QA Level assignment to the activity (AP 5.90 replaces NNWSI Project SDP 03 03 which defines existing data as data generated prior to the August 1980 ver sion of the NNWSI Project DA Plan and theref ore elimi nates much of the core from the existing data category). Also AP 5.90 utilizes the f our methodologies for qualification described in the NRC Generic Technical Position Paper on the "Qualification of Existing Data".
These four methodologies and examples of their application to the drillhole data are listed below. Corroborative Datar A comparison of the petrology of samples ! collected from stratiographic sections at the surface and from I t 8 L
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'd w3 / d i sI[12/ 071589. r p t '/ L i n eh an / LV the _ ESF sample sites with existing drillhole samples is an example.
Conformatory Testing: The application of geophysical logs from the existing dri11 holes to the recognition of stratigraphic units defined -initiall y on the drillhole li thologic logs is an example. QA Program: An activity controlled by procedures similar to a 10 CFR 50 Appendix B Program might be the documented acceptance
' procedures and detailed technical procedures used in the geophysical logging of NNWSI Project drillholes. These may be sufficient to qualify the drillhole stratigraphy.
Peer Review: A panel of experts external to the project who would review a protocol put together by the NNWSI Project. This protocol would be a plan covering the technical methods and-document analyses required for the quali fication of the existing drillhole data. EnDPOSED WORKING GROUP
.The purpose of this group would be to assemble and evaluate documents and technical methodol og i es in support of the qualification of existing data utilizing the guidelines in AP 5.90. This group would develop a protocol for qualifying existing core / cuttings and related drillhole data to be used as primary data in licensing documents. It's members would be drawn from the Sampl e Overvi ew Commi ttee. Project Regulatory Compliance j (Licensing) and Quality Assurance.
III. ByDRQLDgy The activities of the USGS hydrologists, working out of test cell "C", Area 25 of the NTS, are the same as noted last month. IV. sgggugMISIBY In Los Alamos National Laboratory's answer to the WMPO letter concerning the qualification of core, LANL states: Use of Existing Core f or Licensing "Most of the studies for geochemistry require that we characterize all units across the repository block and along possi bl e transport pathuays to the accessible environment. j Single key interval s used in these stud.ies cannot be identified. We need all data obtained to develop a three dimensional model of Yucca Mountain. The studies do fall into two groups, however and these can be discussed separately. 9
dw3/di s k 12/071588. rpt / Li nehan/LV "The least restrict!ve (in -terms of core identification) studies that we'do are essentially generic. It is not necessary to independently identify the core or interval from which the sample came.- The core is characterized using XRD, XRF and petrographic microscope description of thin sections. From this information it can be determined what unit, r.;;d often what lithologic interval within the statigraphie uni t is present. The results
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are tied to li thology. mineral ogy and chemi stry. To demonstrate the appropriateness of the results to Yucca Mountain it need only be demonstrated that the lithology, mineralogy and chemistry of the sampl es used in these studies match the intervals of interest at Yucca Mountain. Sampl es can be taken from' future drill core or the exploratory shaf t as appropriate to demonstrate this relationship. Studies that fall into this category are worption studies and glass dehydration studies. For some of the sorption studies natural state samples have been used, and if those are accepted as DA Level-1 they will provide additional tie points to Yucca Mountain, but this should not be necessary for acceptance of the data for licensing.
"The second category is the one that most Mineralogy-petrology studies fall under. Waxed core has not been used in these investigations. Key samples cannot be identified as it is necessary to characterize sorptive barriers along hydrologically transmissive zones across Yucca Mountain. Identification of the borehol e f rom whi ch the samples came is necessary. Vertical . control to within +-50 feet is desired. If waxed core i s accepted as DA Level 1, selected pieces could be analyzed to coroborate existing data for some activities, but probably would not be of much use for fracture mineralogy. Many samples are examined and interpretations are based on a suite of sempl es rather than single occurrences. Misplacement of one or two samples would have no effect on results. Interpretations are tied to lithology and stratigraphy (independently determined) as well as depth. Data collected is internally consistent within stratigraphic interva'.s and between drill holes. Discussion of internal consi stency is contained in the report by Broxton et al.
(mi l estone TO95 copy enclosed)." Also contained in the handout is a copy of:
"Petrography and Phenocryst Chemistry of Volcanic Units at Yucca Mountain. Nevada: A Comparison of Outcrop and Drill Hol e Sampl es" by D. E. Broxton, F. M. Byers. Jr., and R. G. Warren.
- v. egegs11pBy gNQ1 NEE 81tjQ 10
dw3/ disk 12/071588.rpt/Linehan/LV Both Fennix and Scisson and Holnes and Narver are continuing to work on resolution of comments resulting from the 50% Title I design review. VI. WeSIg esggegg Lawrence Livermore National Laboratory is looking at the implications of DOE's revised definition of "Substantially Complete Containment" as it applies to the waste package. The revised definition is in response to NRC comments on the SCP/CD. VII. egBEQBd8NGE GSSESSdENI The work being performed in the area of performance assessment is centered around finalizing the SCP and writing study plans. I'm not aware of any new work in this area. VIII. SIIE ENVIBQNUENIGL OGI1VIIlgS The project is still waiting for air quality permits before starting work on test pits at Fran Ridge. I'm not aware of any new work in this area. IX. LigCNSING GNQ NBGrQQE INIE88CIlgNS A. During June, three Yucca Mountain Project update meetings were held for the public by DOE and the State of Nevada. On the 6th, the meeting was held in Amargosa Valley, Nye County; on the 7th the meeting was held in Las Vegas at the Aladdin Hotel; and on the 9th, the meeting was held in Reno. The State of Nevada did not participate in the Amargesa Valley meeting. However, Mr. Loux and his staff were present and did participate in the Las Vegas and Reno meetings. I attended the two southern Nevada meetings but I did not go to Reno. The presentations were divided into four parts; introduction, transportation, earth sci ence and socioeconomics. 11
'ow3/dia;s12/071588.rpt/Linehan/LV 8
The DOE presented first with the State following. Each of the four parts were completed in turn. The presentati ons were designed to answer those questions most asked by members of the public. Some examplos are: Why Nevada? When would a repository be built? What's going on now at Yucca Mountain? Why should we believe what DOE says? Would the reposi tory be saf e? Transportation questions concerning routing of waste shipments, safety of shipments including saf ety checks (who makes them, who is responsible?), accident prevention, emergency response (who pays for), and cask design. Socioeconomic questions including employment, expenditures (how much will it cost and who pays for it?), and potential impacts on local infrastructure and tourism. Earth sciences including geology, hydrology and plans for site characteri=ation. A handout i s encl osed. Approximately 60 people attended the Amargosa meeting. Major concerns expressed by the citizens include: l Nye County wants more NTS/repoci tory jobs. More access to union jobs. This was the number one priori ty. 12
9 dw3/ disk 12/07iSB8.rpt/Linehan/LV Bus service to be made available from other Nye County communi ti es. Presently there is bus service from Pahrump. It was also suggested that the subsidy to the bus company be eliminated to make residency in Nye County niore attractive. Most i4TS workers live in Las Vegas, Clark County. Make emergency services available if an accident occurs. About 200 people attended the meeting at the Aladdin Hotel in Las Vegas. Many of the attendees were DOE employees. The major concerns expressed by the public at this meeting were U Siting issues surrounding the repository. Reprocessing of waste. Transportation routes. Evacuation plans for the Las Vegas Valley should there be an accident. Terrorism concern. In Reno, only about 60 people attended. Major concerns expressed include: Shoshone Indian land rights at Yucca Mountain. Nationwide hearings on transportation routes. Volcanic activity near Yucca Mountain. B. On June 7th, I attended the Sample Overview Committee (SOC) meeting at the new Sample Management Facility (SMF) and participated in a tour of the SMF. This i s a very i mpressi ve facility. 13
dw3/ disk 12/071588.rpt/Linehan/LV C. On June 9th I-attended a meeting of the Licensing Support System (LSS)' at the request of Chip Cameron, NRC attorney. The basic purpose of this meeting was to demonstrate for the State of Nevada what' types of "raw data" are being generated by NNWSI. participants. Presentations were given by the USGS, Sandia National Laboratory, Los Alamos National Laboratory and SAIC. Examples of raw data and the instrumentation used to obtain it were set-up as displays. The State indicated that they were satisfied with the demonstration. The agenda and attendance list are attached. Because of my involvement in the June 9th LSS meeting,- I was asked to attend the June 29-30 LSS meeting in Reno, Nevada, to help in resolving the "raw data" question. This i s only one part in obtaining an agreement on the wording of the proposed NRC rule concerning the LSS. The State of Nevada wrote, and proposed for inclusion in the rule, a paragraph describing how "raw data" would be handled in the LSS. The wording of the State's proposal was modi fied and the document was given to all parties for con si dera t i on. D. During the week of June 13-17 I attended the American Nuclear Society (ANS) meeting in San Diego, California. The meeting concluded on the 16th. The ANS is a Nuclear Industry Organization. The waste disposal problem has become important enough to the nuclear industry that a session dealing with the waste problem was scheduled for each time period. The sessions were very well attended. Considering that much of the audience was not directly involved with the repository program, it isn't surprising that the subject matter was presented in a rather basic way. The biggest disappointment to me was the presentation of performance assessment. To me, there was no indication that the different 14
, ' dw3/ d i si: 12 / 071588. r p t / Li n eh an / LV people and organizations working on this problem are coordinating their efforte. This could be the result of the way the subject was presented. I hope so. Enclosed is a copy of the agenda and a description of the sessions concerned with the waste problem. E. On June 28 I conducted a tour of the Test Site for Ms. Joyce Amenta, Deputy Director, Information Resources Management and Mr. Avi Bender. We vi si ted "G" tunnel, Sedan Crater, and Yucca Mountain. F. On June 6th and 20th I met with Mr. Carl Gertz. WMPO Manager. General subjects of interest were discussed. Un the 20th, I was introduced to Mr. Ed Wi lmot, Mr. Gertz's new Deputy Manager. G. Enclosed in a handout from the June TPO meeting held on July 5, is the latest WMPO organization chart. In presenting thi s chart, Mr. Gertz emphasized that WMPO would soon be reorganized and that this organization chart would be obsolete. X. SCE GND SIUDY EL8NS During the June TPO meeting, it was mentioned that there are two new sections to Chapter 8 of the SCP planned. It was stated that thi s could run to 500 new pages. Review and comment resolution workshops with DOE Hg. are scheduled for July 25 through August 19. These workshops are scheduled to be held in Las Vegas. Final production is to ctart on September 9. 1 Final DOE Hg. concurrence review is scheduled for October 24 through November 4. Printing is scheduled between November 21 and December 26 with public release December 28. 15
y dw3/ disk 12/071588.rpt/Linehan/LV Enclosed is a handout and a network for SCP completion. XI. SIGIE IUIERGGIlgNS There were no State interactions except as noted elsewhere in this report CLSS meetings, ANS meeting, public meetings). XII. MISGELLONgQQS DOE-WMPO- i s starting a long range planning effort. The week of Jul y 11 is scheduled for the kick-off. The effort is scheduled to be completed in December. An enclosed handout outlines this effort. Also enclosed is an evaluation of project level management plans. The handout shows how the Project Management Plans relate to the Project Plan and the status of the writing of the management plans. cc: With enclosures: K. Stabl ei n, R. E. Adler, J. E. Latz No enclosures: C. P. Gertz, R. R. Loux, M. Glora, D. M. Kunihero, R. E. Browning, G. Cook, L. Kovach, S. Gagner, K. Turner
Enclosures:
Evaluation of Project-Level Plans Background; Long Range Planning Effort Status; Schedule for SCP Completion; Status of SCP Completion; Agenda, 7/5-6/88 TPO Meeting; TPO Presentation by Carl Gertz, 7/5/88: Excerpts from Transactions, American Nuclear Society Meeting, 6/12-16/88; Licensing Support System Advisory Committee - Participants Meeting on Raw Data. 6/9/88: Yucca Mountain Project UPDATE MEETING, 6/88; Responses to the WMPO core letter; Core Strategy Optiona; Charter for the Sanple Overview Commi ttee; Inf ormal Input, NNWSI Project, Admi ni strati ve Procedure: Informal Input, Boreholes Inventoried at USGS Library through 6/7/88; Revi sion of Participants DAPPs; Audit definition; Procedure Review Checklist; Schedule for Meeting Requirements to Implement a Fully Oualified DA Programa OOAP f 16 i
i EVALUATION OF PROJECT-LEVEL: PLANS I BACKGROUND i i QASC'S REVIEW OF THE FY PRESENTED ON OCT. 22. 1987 ACTIVITIES WAS RECOMMENDATIONS 5 MADE REGARDING: j i e l MANAGEMENT CONTROLS a TRAINING ) e QA STAFFS 4 i e PLANS AND PROCEDURES i e i FY 1987 MANAGEMENT ASSESSMENT I i i
.- PLPWM.8HF/7-6-8@ 9
l EVAL.UATION OF PROJECT-LEVEL PLANS l BACKGROUND (CONTINUED) \ IN RESPONSE TO OCT. 22 REPORT, C. GERTZ DIRECTED T& MSS TO DEVELOP AND ACTION PLAN TO PUT PROJECT IMPLEMENT SYSTEM IN ORDER MANAGEMENT e ACTION PLAN APPROVED FEB. 5
- TEAM APPROACH
- DEFINE DOCUMENT HIERARCHY
- REVIEW, REVISE, OR CREATE PROJECT-LEVEL PLANS e
DOCUMENT HIERARCHY ESTABLISHED EARLY APRIL e BECAME PART OF FULLY QUALIFIED QA PROGRAM REQUIREMENTS IN MAY o , PLAN TO COMPLETE REVIEW AND REVISION OF PROJEC LEVEL PLANS APPROVED BY C. GERTZ ON JUNE 7 - PLPWM.DRT/7-6 00 2
4 TEAM APPROACH THREE TEAMS PLUS A GROUPS WERE FORMEDNUMBER OF WORKING THE TEAMS AND THEIR BY T& MSS AND WMPO. ARE: PRIMARY FUNCTIONS TEAM 1: ; AN OVERVIEW TEAM THAT HAS OVERALL RESPO FOR IMPLEMENTATION AND COORDINATION OF EFFORT. AND WILL PERFORM INITIAL REVIEWS OF AL . t i TEAM 2: A REVIEW SYSTEM TEAM ELEMENT WITH INTEGRATION PRIMARY RESPONSIBILIT LEAM_ 3; A CONCURRENCE REVIEW TEAM TO PROVIDE FIN NICAL AND MANAGER POLICY REVIEW PRIOR TO NNWSI PROJ APPROVAL t PLPWM.BBF/74 00 3
v TEAM APPROACH (CONTINUED) 'I WORKING _ GROUPS: . 1 l A SMALL GROUP OF T& MSS STAFF TO REVIEW EXISTIN { DOCUMENTS AGAINST AGREED-UPON REQUIREMENTS, TO IDENTIFY DEFICIENCIES (IF ANY), AND TO REVISE / PREPARE DRAFT DOCUMENTS FOR REVIEW i i i I n ewu unr/7 s as 4
TEAMS TEAM 1: W. MACNABB - CHAIRMAN M. KUNICH - DEPUTY PROJECT MANAGER, WMPO M. FOLEY - PROJECT OPERATIONS M. GLORA - REGULATORY COMPLIANCE D. JORGENSON - TECHNICAL INTEGRATION J. ESTELLA - QUALITY ASSURANCE F. GOWERS - PROJECT MANAGEMENT J. FIORE - PLANS AND PROCEDURES (SUPPORT) TEAM 2: M. VOEGELE - CHAIRMAN D. DAWSON - REGULATORY COMPLIANCE P. MUDRA - PROJECT OPERATIONS S. KLEIN - QUALITY ASSURANCE 1 R. LARIVIERE - SUPPORT SERVICES C. JONSON - PROJECT MANAGEMENT TBD - WASTE MANAGEMENT PROJECT OFFICE TEAM 3*: M. SPAETH - CHAIRMAN W. DIXON - CHIEF, SYSTEMS & PROJECT CONTROL BRANCH, WMPO M. BLANCHARD - CHIEF, REGULATORY & SITE EVALUATION BRANCH, WMPO L. SKOUSEN - CHIEF, TECHNICAL DEVELOPMENT & ENGINEERING ,BRANCH WMPO J. BLAYLOCK - QUALITY ASSURANCE DIVISION, DOE !
- MEMBERSHIP AS REQUIRED BY QMP-06-03 OR AP 1.10 AS APPROPRIATE PLPW'1 BIV/7-6 88 S l
SIMPLIFIED FLOW CHART (START) V U DEFINE THE PROBLEM PREPARE DRAFT PLANS U V DEFINE THE APPROACH FEB. 5,1988 SEP.30,1988 REVIEW AND APPROVE U DEFINE THE DOCUMENT HIERARCHY TRAINING AND SPECIFICATIONS APR. 8,1988 7_________ y REVIEW AND EVALUATE EXISTING DOCUMENTS (END ) i SCHEDULE TBD p 1 PRIORITIZE ANY U REVISION OR CREATION OF DOCUMENTS V CD PLPWMN18/7-6 88 6
l MANAGEMENT SYSTEM'S PLAN ' HIERARCHY AND BASIS t DEFINITIONS e PROGRAM AND POLICIES P_OLICIES CONTAINED IN&THE BEQUIREMENTS_ LAW, IN DOE,AND ORDERS A IN DOE /HQ GUIDANCE THAT DEFINE ROLES, RESPONSI - ITIES, AND COMMITMENTS BETWEEN DOE /HQ AND TH OFFICE e PROJECT P_QLICIES & REQUIREMENTS AR BY WMPO TO THE FIELD OFFICE THAT DEF DONE TO SATISFY THE AGREEMENTS THE FIE MADE WITH PROJECT DOE /HQ AND BY WHAT S'/ STEMS WILL BE MANAGED i e I ARE THE DIRECTIONS WMPO PR MENTS WILL BE SATISFIEDPROJECT AS T - __ _ . ___ . - - _- - - - - - "' ""'S " S '" * " '
PROGRAM POLIC:ES & REQUIREMENTS- DOE /NV's COMM:TMENTS TO DOE /HQ PROJECTPLAN PROJECTMANAGEMENTPLAN PROJECT POLICIES & I REQUIREMENTS TO ENVIRON- . MEET DOEA10 - WMPO AWANCED MENTAL FINANCIAL & TEST & PERFORM-j COMMITMENTS TO DOE /NV, ACO.OR SAFETY & EVALU- ASSIS- CONFIG. ANCE "WilAT' WILL BE DONE & HEALTl1 SEMP RECORDS ESF ATION PIAN STANCE MGMT. OAP MEAS. TRAINING I(OW MANAGED PROTEC- MGMT. MGMT. PIAN PLAN . APPLICA- M G M T.
- TION IMPL ' PLAN PIAN
*
- TION PUVI PLAN PLAN IT4PLEMENTING PLANS AND PROCEDURES - WMPO DIRECTION TO PROJECT PARTICIPANTS ON "llOW' QUALITY ASSURANCE PROCEDURES POLICIES AND REQUIREMENTS ADMINISTRATIVE PROCEDURES OF UPPER LEVEL PLANS WILL TECHNICAL PROCEDURES BE SATISFIED
- CALLED OUTIN DOE ORDER 4700.1 AS ANNEXES TO Tile PMP m sn our ocoa
TEAM 1 AND TEAM 2 FINDINGS CURRENT STATUS OF PLANS STATUS: PLAN NAME & ",* " ' DATE OF LATEST EXISTS AS A ESTIMATE OF PRIORIT'Ir VERSION A= APPROVED AS FINAL EFFORT FOR FOR SUB-F=WMPO APPROVED COMMENTS ON OVERALL ADEQUACY WORKING GROUP SEQUENT
* " PLAtt REVIEW / REVISION EFFORT F _.
AN UPDATE IS NEEDED TO MAKE THE 53MM CONTENTS MATCH THE REQUIREMENTS 2 OF 4700.1 AS MUCif AS POSSIBLE AND TO REFLECT RECENT LEGISLATION
.mCT MANAGEMENT F I
SAME COMMENTS AS ABOVE EXCEPT
.2/67) $3MM 2 LEVEL OF DETAll IN SOME AREAS NEEDS EXPANSION 4
TEST & EVALUATION F Pt AN CURRENT ANNEX TO PMP ADEQUATE, BUT * (12/87} 3 IS OUT OF DATE - NEEDS UPDATING AND EXPANSION ADVANCEO ACQUISITION F OR ASSISTANCE PLAN CURRENT ANNEX TO PMP NEEDS TO BE
- g 12/87)
REVISED TO MEET 4700.1 REQUIREMENTS; 3 MANY PARTS OF THIS PLAN WILL DOCU-MENT PAST ACOUISITION EVENTS AND FINANCIAL ASSISTANCE PLANS FOR THE STATE AND UNITS OF LOCAL GOVERN-MENTS ENVIRONMENTAL, F SAFETY, HEA'_Til CURRENT ANNEX TO PMP NEEDS PROTECTION REVISION AND UPDATING TO REFLECT $3MM 2 IMPLEMENTATION PROJECT APPROACH POSITIONS AND REGULATORY SEMP A (11/87) APPEARS TO DE ADEQUATE
$ 1MM 1
*lNCLUDED IN ESTIMATE FOR PMP PLF%tA PtJB/7 6 e8 10
TEAM 1 AND TEAM 2 FINDINGS CURRENT STATUS OF PLANS (CONTINUED) STATUS: PLAN NAME & # " DIEYlS S AS DR ESTIMATE OF PRIORITY DATE OF LATEST EFFORT FOR VERSION A= APPROVED AS FINAL COMMENTS ON OVERALL FOR SUB-F=WMPO APPROVED WORKING GROUP SEQUENT ADEGUACY CONFIGURATION REVIEW / REVISION EFFORT D MANAGEMENT PLAN APPEARS TO BE ADEQUATE; NEEDS TO DE (2/88) ISSUED 5 1MM 1 OUALITY ASSURANCE A PLAN, 88-9, REV. O APPEARS TO BE ADEQUATE; SUBMITTED (N/A) TO NRC FOR REVIEW 5 1MM 3 FINANCIAL AND N PERFORMANCE NO CURRENT DOCUMENT EXISTS TO MEASUREMENT MEET PROJECT NEEDS 3-5 MM J APPLICATION PLAN RECORDS D MANAGEMENT PLAN CURRENT DOCUMENT IS WRITTEN TO (6/88) s 1MM 1 DRAFT HQ GUIDANCE PASSED DOWN FROM ESF MANAGEMENT PLAN EXISTING APPROVED DOCUMENT OUT-(7/83) 53MM 1 A DATED DATE AND SHOULD BE BROUGHT UP TO (6/86) D TRAINING F MANAGEMENT PLAN APPEARS TO BE ADEQUATE (5/88) 5 1MM 1 TOTAL LOE 5 20-23MM PLPWM PUD /7 608 11
7/6/88 PM/TP0 MEETING STATUS OF SCP COMPLETION INTEGRATION GROUP BRIEFED HQ MANAGEMENT ON 6/21/88 HQ MANAGEMENT CONFIRMED DOE'S COMMITMENT TO MEET THE DECEMBER 1988 RELEASE DATE FOR THE STATUTORY SCP INTEGRATION AND WORKING CROUPS WERE DIRECTED TO PLACE HIGilEST PRIORITY ON COMPLETION OF REVISIONS TO THE SCP/CD IN RESPONSE TO THE NRC & USGS COMMENTS
d PAGE 2 7/6/88 PM/TP0 MEETING l l STATUS OF SCP COMPLETION INTEGRATED ACTIVITY-LEVEL NETWORKS HAVE BEEN PREPARED FOR SITE ACTIVITIES IN THE SCP/CD
+
MAJOR CONSTRAINTS ON SITE ACTIVITIES ARE THE DRILLING SCHEDULE AND THE ESF CONSTRUCTION SCHEDULE NETWORKS FOR SCP/CD PERFORMANCE AND DESIGN ACTIVITIES NEED FURTHER ATTENTION BEFORE THEY CAN BE INTECRATED WITH THE SITE ACTIVITY NETWORKS
PACE 3 7/6/88 PM/TP0 MEETING STATUS OF SCP COMPLETION PRELIMINARY ESTIMATES OF SCP/CD ACTIVITY COSTS COMPARE FAVORABLY TO SITE COMPONENT OF 1990 WAS/FWP = HOWEVER: SCP/CD NETWORKS AND COST ESTIMATES DO NOT CONTAIN INCREMENTS THAT MAY BE REQUIRED TO RESPOND TO NRC OR USGS COMMENTS THE NETWORKS AND COST ESTIMATES WILL NEED TO BE REVISED AFTER THE STATUTORY SCP IS IN FINAL PRODUCTION SCP WORKING CROUPS WILL TURN ATTENTION TO REVISION & REFINEMENT OF NETWORKS AS SOON AS TEXT REVISIONS ARE COMPLETE
PACE 4 7l6l88 d jwdc vi l ' ^' PM/TP0 MEETING ;. tin j;,j.;
-llcao.no w O g,xl3-) :
l i PLANS FOR PRODUCTION OF THE STATUTORY SCP )
. ALL TEXT REVISIONS AND RESPONSES TO COMMENTS ARE DUE TO THE j INTEGRATION GROUP BY JULY'3, 1988 i
i
- POTENTIAL PROBLEM AREAS INCLUDE j -- CHARACTERIZATION IMPACTS ON ISOLATION /8.4 REWRITE
-- ACTIVITIES THAT MAY EXTEND BEYOND 1/95
-- TEXT REVISIONS RELATED TO ALTERNATE CONCEPTUAL MODELS
PAGE 5 PM/TP0 MEETING 7/6/88 PLANS FOR PRODUCTION OF THE STATUTORY SCP e INTEGRATION GROUP WILL MEET JULY 18 TO JULY 22 TO PREPARE AND REVIEW THE CONSOLIDATED MARKUP; THE MEETING WILL CONTINUE THE WEEK OF JULY 25 AS NECESSARY HQ REVIEWS AND COMMENT RESOLUTION WORKSHOPS WILL BE SCHEDULED FROM JULY 25 THROUGH AUGUST 19: CURRENT PLANS ARE FOR WORKSHOPS TO BE HELD IN LAS VEGAS INTEGRATION AND WORKING CROUPS WILL WORK WITH SCP PRODUCTION TEAM TO PREPARE INTEGRATED MARKUP FOR FINAL PRODUCTION TO START ON SEPTEMBER 9 i
Nv.- PAGE 6 PM/TP0 MEETING 7/6/88 PLANS FOR PRODUCTION OF THE STATUTORY SCP FINAL HQ CONCURRENCE REVIEW IS SCHEDULED FOR OCTOBER 24 TliROUGH NOVEMBER 4 PRINTING OF FINAL DOCUMENT BY GP0 WILL BE SCHEDULED BETWEEN NOVEMBER 21 1 DECEMBER 26 WITH PUBLIC RELEASE SCHEDULED FOR DECEMBER 28
' INFORMAL INPili Paat. Ausmar -
AGENDA N-AD-028 MNWSI PROJECT T1ANAGER-TECHNICAL PROJECT OFFICER MEETING /86 LOCATION: 101 Convention Center Drive PACE: 1 Las Vegas, Nevada DATE: JULY S-6, 1988 TIME %11AT 110W 4110 EXPECTED REF. MATERIAL OUTCOME & COMMENTS To:sd:y July S 1:00- 1:1S INTRODUCTION / ROLES AROUND Tile ROOM ALL AGENDA /0UTCOMES REVIEW, REVISE, ACREE JOY /ALL AGENDA AND OUTCOMES TliAT u1NUTES SENT ALL ACREE TO APPROVED 6/23/88 MINUTES MINUTES-MAY ADJUST, AGREE J0Y 1:1S- 1:45 MANAGER FYIs PRESENT FYIs CARL UNDERSTAND STATUS OF FYI ITEMS 1:45- 2:45 FYIs PRESENT 5 MIN FYIs AROUND BR OlFS/TP0s UNDERSTAND STATUS OF FYI Tile TABLE ITEMS 2:45- 3:00 BREAK 3:00- 3:30 AUDIT PROCESS PRESENT AUDIT PROCESS STAN KLEIN UNDERSTAND PROCESS FOR DOING AUDITS 3:30- 4:00 PARTICIPANT QUALITY PRESENT MATERIAL ON QUALITY STAN KLEIN UNDERSTA'iD PARTICIPANT PROCEDURE REVIEW REVIEW PROCESS ROLES IN QUALITY PROCSS DESCRIBED IN PROCEDURE REVIEW PROCESS QAP 4:00- 4:30 QA RELATED STEPS AND PRESENT QUALITY RELATED STAN KLEIN UNDERSTAND SOiEDULE SOiEDULE FOR PUTTINC IN STEPS AND SCffEDULE FOR PROCESS AND PARTICIPANT PLACE A QUALIFIED QA QUALIHED QA PROCRAM ROLES PROGRAM
AGENDA N Nt-IS I N-AD-028 PROJECT MANAGER-TECHNICAL PROJECT OFFICER r1EETIMdi /86 g LOCATION: 101 Convention Center Drive PACE: 2 l Las Vegas, Nevada DATE: JULY 5-6, 1988 TIME WHAT HOW EXPECTED REF. MATERIAL WHO QUTCOME & COMMENfS Tussday July 5 4:30- 5:00 NON-QA STEPS AND PRESENT NON-QUALITY RELATED MACNAB8 UNDERSTAND SCHEDULE SCHEDULE FOR PUTTING IN STEPS AND SCHEDULE FOR A PROCESS, AN3 PARTICIPANT PLACE A QUALIFIED QA QUALIFIED QA PROGRAM ROLES PROCRAM 5:00- S:30 NEED TO QUALIFY PRESENT INFORMATION ON UEL CLANTON CLARIFY WHAT WAS j EXISTING SAMPLES EXISTING SAMPLES REQUESTED, WHAT WAS ! RECEIVED, WHAT WILL BE DONE WITH SAMPLES S:30- 6:00 INTRODUCTION OF NRC PRESENT CILRAY AND
SUMMARY
JOHN LINEHAN UNDERSTAND HIS ROLE AND REPRESENTATIVE CILRAY OF HIS ROLE DUR INTERACTION WITH HIM 1 I i j i
gi L A I 8 S 2 8 R T 0 8 E N
- 9 T E D 1 AM A6 MM 8 , O N/ 6 F .C 5 RE &
Y l I E D 3 U R NN J EM D A LAO LA E P A I
- : ORTSR E CST F E E RGCAI R IUA O C T OE U P S PTT N A A SRJYQ OT YAN EI P D TPOHE OTN TTE M D C RCR T E ESS OG E E EAPR WM H E CN FQ AT EON CYR TI G T M C O F NRR NHG RTP UT N E C EDOEO O IE AI OE I P T E IFE ENSD VN E X U DITHFT MOSI DIU DM T EO NFC EE O AW NTR N E AIAT L SL - AC AG TLPNSP ALT TAY TN E SAMEAM NSOC S R SIR 1
r RUIM O CORE RYD RLE EQ ULC IPTJ ED ELV D DCL SONO DUE DIN R NNNOEO SROR NTE NRE UIADWT APCP USS UDD E C I F B B S N F A S E O ER O O C N Y S YE H A B AT W A H O HN T M D U C L Y R E YH R E L R V RM J I B A A AO O L D LT R AP D S
~I NL T' P S
N E E A AE
) M GC I HT WS T
U AT N I RG E A N 6 B TI N M OA FN H FT AOUO 5 A OX DOP 1 LM C W YN E S H ( A E 0 NOTL - SO E 1 R RTIO S RT M T 1 AD E WR U A O
- MN CF T T EN C MA NFSN A HO T R U OATO T EI U E SE CTNC S RT D N A G TO T S. ML E T TT T A E ND NCNA N NN N N ENGR E EE E SN SIIT S SS S A EE RE EKSN E EE E N RSSE R RR R PB PAAC P PP P T e v
C i N N _ E r T C O I O J D E I T T N T S _ O r J O C T Y A I X MN R e A C D T E EO t R SE U N G N TI P n PD FTJ TS E N IT e a T N ONO SU S I F A I C d A FA ER T ET T O NU a l O NMP LA RN E SOL S n v i W NNS S ON IGT AT CS PE M E TMIA o e M S SETV M i N OAE TIU I " E M ITCE _ N t ILR TPU ASO NSH PY NG G E LIA N n , YT UA N T G e s A D IAG TI RN IR I WAWN ULE v a D U EV A LE EDEI n g LEC RMO l iI YM LV N INIT o e AVO OER CT R IN E VEVE C V VER OTH RC DO RE P ECEE ELP CIT AA " T DD O RARM 1 s 0 a 1 L 0 0 0 5 5 0 _ N E y a 3 9 0: 0 1 1 3 O M 0 1 1 2 2 I I d 1 1 1 1 1 T T s6 - - - - - - A e 0 0 0 0 5 S C n y0 3 0 0 1 1 O dl : : : : : : L eu9 9 0 1 1 2 WJ 1 1 1 1
=_ ._ _- - . _ _ - -- - .
l I TPO PRESENTATION I 1 PRESENTED BY l Carl Gertz a 4 1 JULY 5,1988 a I? I i b Ik Bo at
'I 1
- .4
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i l AGENDA f j i e PROJECT UPDATE MEETINGS j e AMERICAN NUCLEAR SOCIETY MEETING j e ACNW MEETING e DENVER SCP MANAGEMENT MEETING j e UPDATE ON STATE GRANT ' l e QA/QC GENERAL l - QAPP MUST MEET SCHEDULE l e FOREIGN INVOLVEMENT / BOARDS, ETC. i o TOURS AND SUPPORT OF e CALENDAR INPUT e USGS DENVER AUDIT - BRIEF STATUS e OTHER OUTREACH ACTIVITIES e WMPO REORGANIZATION STATUS
- YUCCA MOUNTAIN PROJECT '
l
e i 4 ! YUCCA MOUNTAIN PROJECT l UPDATE MEETINGS i l i j AMARGOSA VALLEY JUNE 6,1988 t LAS VEGAS JUNE 7,1988 i { RENO JUNE 9,1988 WPOWD.13ilf/6 21-88
I l AMARGOSA VALLEY LOCATION: COMMUNITY CENTER I SIZE OF AUDIENCE: 60 PEOPLE MEDIA PRESENT: PAHRUMP VALLEY TIMES , NOTE: STATE OF NEVADA DlD NOT ATTEND THIS MEETING WPOWD.ORF/6 21-88
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Y 8 8 - R 1 2 6 O
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O F R B. T I T D W O S O E P W O T C S P I F N E S V I R R T R E / S N E E _ B L C S S B N T O M TY A N J S O ON U L C E N FRU B I A Y R O O V E O I N EC D A L M L E L U BE Z S A S AY I E O LN D C V T T I I S I S N AN V R A A S VI B R U S S AS U E O WS E S SC G Y B C ET S C R TO C CN E T A YO A N J A I VO I AG C M UT RP N V E NT A OC E E I EN CEJ R SR MS GE O E I LA RD I EO M SH EL EC YR UT MC NP - BO - EA e o o i
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F l, D N 0 D
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YS T i P W TE , I RIV A I S OT R S JA E E L A EL P A V M I E (R P T T S A O ED T W
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S H LN N A E S G N PA E E O NN S V I D EY LO E D P L I AIT R - P S A 0 M CA E A L 0A OT R L A 2F LS A
- D T A N V E E -
E S N
- C E N F N R O A P O I
D , T N A E A E I T - C I D A O l E T L A M S -
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LAS VEGAS CONCERNS e SITING ISSUES SURROUNDING REPOSITORY e REPROCESSING e TRANSPORTATION ROUTES e EVACUATION PLANS FOR LAS VEGAS VALLEY e TERRORISM CONCERNS WPOWD.B AF/6-21 88
1 1 RENO 1 LOCATION: RENO / SPARKS CONVENTION l CENTER l l ATTENDANCE: 60 PEOPLE MEDIA PRESENT: RENO NEWSPAPER, TV STATIONS 1 STATE OF NEVADA REPRESENTATIVES ATTENDED WPOWD.ltitF/6 21 atl
RENO CONCERNS e SHOSHONE LAND RIGHTS AT YUCCA MOUNTAIN e NATIONWIDE HEARINGS ON TRANSPORTATION ROUTES e VOLCANIC ACTIVITY NEAR YUCCA MOUNTAIN WPOWD.BRF/6-21 -88
t}l. , '\"m ? RL-' W- AAw' *s r A "W L' AE[Nh*~1A Y m .M" _ i PRESENTATION TO l ADVISORY COMMITTEE ON NUCLEAR WASTE l - DOE / NEVADA ORGANIZATION INTRODUCTORY REMARKS-ALTERNATE CONCEPTUAL MODELS CONCLUDING REMARKS i PRESENTED BY Carl Gertz MANAGER YUCCA MOUNTAIN PROJECT LAS VEGAS, NEVADA FTS 544-7920 (202) 794-7920 JUNE 28,1988 m- _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - . _ _ _ _ _ _ .
BACKGROUND / STATUS OF THE l DRAFT REPORT BY JERRY SZYMANSKI (DOE)
"CONCEPTUAL CONSIDERATIONS OF THE DEATH VALLEY GROUNDWATER SYSTEM..."
i e SUBJECT ! - CONCEPTUAL MODEL FOR THERMAL & TECTONIC INTERACTIONS l WITH GROUNDWATER IN THE SOUTHERN GREAT BASIN l e ORIGIN OF REPORT DISCUSSIONS WITH PROJECT SCIENTISTS DOCUMENTATION: NEED, REQUEST l o AN EARLY, UNREVIEWED DRAFT WAS RELEASED } - MEDIA / POLITICAL PARAPHRASING CREATED CONFUSION i j e REVIEW PROCESS j - STANDARD QA REVIEW: COMMENTS & RESOLUTION l - EVALUATE POSSIBLE IMPACTS TO PROJECT APPROACH PEER REVIEW REPORT STATUS PUD 6/2t/08 ., i
STATUS OF PROJECT PEER REVIEW e REV! EWERS PROJECT: DIVERSE EXPERTISE (USGS, LANL, SNL, SAIC)
- OTHER: NAS, NRC (ACM WORKSHOP), STATE OF NEVADA e COMMENTS & COMMENT RESOLUTION
- TOPICS: HYDROLOGY, FLOW PROCESSES, THERMAL CONVECTION, VOLCANISM, TECTONICS, ROCK MECHANICS, GEOCHEMISTRY, UNEs AT NTS
- RESOLUTION PROCESS: INTERDISCIPLINARY SCIENTIFIC INTERACTIONS
- STATUS: MAJORITY OF TOPICS ADDRESSED @ ~ 100% RESOLUTION
- RESOLUTIONS: CLARIFICATIONS, ALTERNATE INTERPRETATIONS, SIGNIFICANCE e PLANS FINISH RESOLVING COMMENTS & DEVELOP PEER REVIEW REPORT
- CO-AUTHOR SYNTHESIS REPORT TO CLARIFY TECHNICAL ISSUES EVALUATE ADEQUACY OF SITE CHARACTERIZATION PLANS STATUS. PUB 6f208
i j i THE PROJECT'S PERCEPTION OF THE ! GEOLOGICAL ENVIRONMENT IS EVOLVING. l THERE IS A MANAGEMENT COMMITMENT TO INTEGR. ATE EVOLVING HYPOTHESIS INTO THE PROJECT I e JERRY'S CONCEPTS THAT STRESS AND TEMPERATURE ARE l INTEGRAL COMPONENTS OF HYDROLOGIC BEHAVIOR ARE I NOW BEING FULLY INTEGRATED AT THE PROJECT WORKING LEVEL ! e HEALTHY TECHNICAL DISAGREEMENTS ABOUT THE POTENTIAL j MAGNITUDES OR FREQUENCY OF SIGNIFICANT HYDROLOGIC j EFFECTS ARE BEING EXPRESSED BY VARIOUS SCIENTISTS J ! e THE TECHNICAL INTERACTIONS DURING THE REVIEW PROCESS l HAVE BEEN BENEFICIAL TO THE PROJECT'S SCIENTIFIC l THINKING, AND SOME OF THE CURRENT DISAGREEMENTS ABOUT SIGNIFICANCE MAY BE RESOLVED AS THE REVIEW
- PROCESS IS CARRIED TO COMPLETION; PLANNED TESTING j WILL RESOLVE OTHERS l
MANAGEMENT IS COMMITTED TO A COMPREHENSIVE SITE INVESTIGATION PROGRAM l l l l e WE RECOGNIZE IMPORTANCE TO POWER INDUSTRY & SOCIETY e MANY TECHNICAL REQUIREMENTS ARE UNPRECEDENTED
- THEREFORE, PERCEPTIONS AND APPROACHES WILL BE EVOLVING e WE WELCOME INPUT FOR WAYS TO REFINE CURRENT APPROACHES e WE WILL RESPOND AS APPROPRIATE TO CLARIFY OR MODIFY PROGRAMMATIC PLANS
i STATE OF NEVADA GRANTS ! FOR INDEPENDENT STUDIES AND PARTICIPATION IN SITING PROCESS i i PERIOD AMOUNT STATUS _ 3/87 - 6/88 $14.1 M APPROVED 7/88 - 6/89 $23.1 M PROPOSED 7/89 - 6/90 $26.7 M PROPOSED 7/90 - 6/91 $31.4 M PROPOSED PitJSTAT2.13f tF/6-23 88
U.S. CONGRESS PASSED THE FY 1989 ENERGY AND WATER DEVELOPMENT APPROPRIATION BILL WHICH NOW LIMITS STATE OF NEVADA GRANT TO S11 MILLION FOR JULY 1988 JUNE 1989 e BILL CAPS STATE'S TRANSPORTATION STUDIES AT $1.5 MILLION e ALLOCATES ADDITIONAL $5 MILLION FOR GRANTS TO LOCAL GOVERNMENTS FOR INDEPENDENT STUDIES e NO FUNDS CAN BE USED DIPECTLY OR INDIRECTLY TO INFLUENCE LEGISLATIVE ACT!ON BEFORE CONGRESS OR A STATE LEGISLATURE OR FOR ANY LOBBYING ACTIVITY - e UP TO $6 MILLION PROVIDED TO UNLV FOR COMPUTER FACILITY TO INCORPORATE BOTH THE LSS AND INDEPENDENT RECORDS MANAGEMENT SYSTEM
GRANTS TO "AFFECTED" UNITS OF LOCAL GOVERNMENT e CLARK COUNTY DESIGNATED AFFECTED LOCAL GOVERNMENT
$4 - $5 MILLION GRANT REQUEST ANTICIPATED e LINCOLN COUNTY DESIGNATED AFFECTED LOCAL GOVERNMENT GRANT REQUEST ANTICIPATED o NYE COUNTV IS THE SITUS COUNTY MEETING SCHEDULED TO DISCUSS GRANT l'f!JS TAl 2.Dilf/6 80
armaan caer esLosu.rewe Amendmem Ns. M Reported m tecW dtsagnemtei. The manaam of tae part of the House wtU otter a mouco to recede and H 4642 CONGRESSIONAL RECORD concur m the amendment of the senate - HOUSE Jurte H,1.988 a ruch groudeS certUn lumt.auons on the uve of Congress in the Fiscal Year 1HT that the duaJ sittna n.pproach does not ' Nuclear Waste Dup <saJ Pund. An amount not to exceed 8U.000.000, at Energy and Water Development Appropria- n.ny way meen cuchcaung a full-ecmae o t an annuallzed rate may be provided to the uorts Act to evaluate the une of lead in hieb- at a second sate. Rat.her. It assumes that State of Nevada for the period July 1.1944 level nuclear state *m=8 canisters. The aggregate capacity reGturement.s he be. Broothaven Nauonal LAborator7 (BNU tween the two sites via trw r==<=s through June 30.1900, for the conduct of its study undertamen as a result of thia diree- e( ovetstsht responstbtllues pursuant to the tive dJd not conalder current technolo61es smaller units. IncJeding moduja.r Nwtaar Weste Poucy Act of 1M2 Pubbe such as those betng developed in Canada. tion. lav 9 % 424. as amended. Further, an Sweden. Belstum, and Argenuna, as well na amount not to exceed Sr.000.000, at an an-nualaned rate. may be seweided to affected in the United States, to determine whether loca.1 governments, as defined in the act. to or not t:us would be a vtablo techno6ogy in conduct appropriate acuviues pursuant to the United States' pers:Anent wasta repod-tory project. the act. Of the 811.000.000 provided to t.he State T!.erefore, the certforees direct that from of Nevada, an amount not to exceed within this nuclear waste *=pa' mal fund so. 81.503.000 Inay be expended ori traitsporta. propnauon, up to $500.000 be for pimmt uoc annanom of which 41.000.000 ta for etud- and amemment activtum to review the BN1-les and asmeestment of transportadon needs studies in regard to recent interna 2tanal and requirementA in conneeuon with the wort in this rub)ect: Identify addHJonaJ in-movement of nuclest waste within the State formauon required; este. bush a peer review of NWt at the Universty of Nevada. Reno panel to review and recomme.nd a&propriate or other appropriate place as determined by research taata t. hat must be taken to com. the State. plete the etsJuadoo directed in the Fiscal It was never the intent of Congrees thaA Year 1981 Energy and Water Developenent the State of Nevada. or any voltmteer 8 tat
- Accroprtations Act. The panel abould in-
.i Indian tdt:e. wisduct its sur. Mte entra- etude sporocriate scienuf)c and tec*uuenJ ter zauon prosTam. Orsat fundtrig provided persona from DOE and namMafad Laborato-pursuant to the act ts to be used solely for ries, BNL and DOL the Buresu of Mines.
the purpose of oversight of the Department s.nd individuals having relevant empertise, of 1.herry's program. Such oversight is not for example. Internauonaj lead Etne Re-Lntended to duplicate data collection done search Organization. ---
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by the Departrnent of Energy. It la further the intent of Congrees that trunt funds are to be spent to the manmum extent practJ. cable within the State of Nevada. The Com-mntee does not intend that grant funds be used to support 'nultastate efforts or tw cr> alluce bMLHr4 with respect to the trans-portauon of nuclear waete to a repository in Nevada. Further. such grant funds sha!] cot be used to appor* dLrectif or indirectJr. lo amytr4 mctiv1ues. subject to une seine pro-hattuans of la U AC.1913 An Adnsory C-~9" en Elan IAvel Waste ihnamg Support erstem has been
==s h f assa:e Septesmear 1987 an a aerosta&.
ed ruksersaing 6f tDe Nue6 ear Regulatoryi h*aa The elect of this rujemamms. na es provide the Wee for e"ms i for a ucene to sessere and proeres hJgh-i level radioscure wome and spent nwie-! fuel at a geoloste'rgpeCoty that will be - basd on an eiertroede @af teq r.ariaM. mest eystan eaDes em Stec.1stng rupport system (Iml that wtB contam material frors the be*".ee applicant-the Depertmetn of Energy-Its contractore, and all other po-teettial parbeiennta in the high-level redlo-actrve waste umnsmg procoe:Itng. It is pees-ently intended t. hat IAS wttl act be part of any am== system that te emetreemd try an,v g.4enuel partaespaat to the histHeegt vast.e reposatory posnetng proceeding, per shcend uee IAS be physsently located ce the pr==a=== el any of Alas possound partJe6-poets. Neverth=tmuL 005 er esaur possuttaa paruegests would est be produded itve= - seems the Im computer fadijty for al recordseesseement systema Independent toi the 1A The conferees agree that fundsi previded in the fiscal year 1980 appresPrts-uon are to be used to suuste tans wars tnI t.his ftamal year and that the UnWersKy ef f Nevada /tAs Versa be destensted as the site of the computer facillty that woeM temapo-saae both the 1.88 and indeissahat records managesnect systeen of othee potecual par-tkcassete tr.ituding the Department and the MMC. I.mences of the IM at the CaMerurty of Iserada/taa vegne is est latended to pre-etude 16 freue .bswe'!'t a esentracter to DOE. An amount of up to $d.Setwe84 is abede eredeWe fer tas puryvee had to worit ' eut a 80egesauce alTangsuneet utta the uni ' wrety are cana-sed vt&h the lina-DF DOE la respease te the diree-
NAS Nominees to Nuclear Waste T ec hn ic a l Review Board (38) Name D is c ipl in e Affiliation Abkowit z , Mark T r an s po r t a t ion Vand e r b il t Allen, Clarence Geology Calif. Inst, of Tech. Berner, Robert Geochemistry Yale Brekke, Tor Geomechanics Calif o rn ia , Berkeley Cantion, John Env ir o nme n t al Science Michigan State Carnesale, Albert Public Policy Harvard Carter, M elv in Rad iobiology/ Health Phys. Georgia Tech Catlin, Robert Radiobiology / Health Phys. Elect. Power Research It Culler, Floyd Chemical & Nuclear Eng. Elect. Poeer Research Ins Deere, Don Geomechanics Consultant, G a in e.sv ill e !
- Eaton, Gordon Geology Iowa State
- Flawn, Peter Geology Texas, Austin Greenwood, Ted Public Policy Columbia Gustafsen, Louis Geology Consultant, Reno NV Holland, Heinrich Geochemistry Harvard Jefferson, Robert T r an spo r t a t io n Consultant, Al bu qu.e r gq e s t Langmuir, Donald Geochemistry Colorado School of Mines Lee, Kai Public Policy Washington Moeller, Dade Radiobiology /Healt h Phys. Harvard (Public Health)
Morgan, M. Granger Systems Analysis Carnegie Mellon Neuman, Shlomo Hydrology Arizona North, D. Warner Systems Analysis D ec is ion Focus, Los Al t c. Pigford, Thomas Ch em ic a l & Nuclear Eng. California, Berkeley Pinder, Georgo Hydrology Princeton Price, Dennis Transportation V ir g in ia Tech Rasmussen, Norman Checidal & Nuclear Eng. MIT' Remson, Irwin Hydology Stanford 4
NAS Nominees to Nuclear Waste Technical Review Board (cont.)
-Name Discipline -Affiliation Rice, James. Geology Harvard Salamon, Miklos Geomechanics Colorado School of Mines Schmitt, Harrison Geology Consultant, Albuquerque N M.
Sherby, Oleg Repos. Eng./ Materials Sc1. Stanford Staehle, Roger Repos. Eng./ Materials Sci. Minnesota Tschinkel, Victoria Environmental Sc ienc e Landers, Parsons-Tallahassee Verink, Ellis Repos. Eng./ Materials' Sci. Florida von Winterfeldt, D. Systems Analysis So. California White, Gilbert Environmental Science Colorado Wiltshire, Susan Public Policy J% Assoc., So. Hamil' ten MA
- Wolman, M. Gordon Environrental Science Johns Hopkins
- Also recommended to chair the Board.
Note: There are 11 disciplines represented with 3 nominees from each except Environmental Science and Public Policy which have 4 nominees and Geology which has 6 nominees. l l l I l_
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' ade Benchmark Reecent Analysse and (Jacetenties Thermes (4.eceoe Design. Anatysle and Design Meehede vei.deolon. end Analysis and Design Nuclear Data and Theemel Reactor COU M Ope svag E penance or feesenech and of iteneaech and L.sstsume.stauen Test Reactors wP*e To.s Reaciors whh sewwe Act.ident Reen.ed Entshmene Phoe.o.viene Reduced f anchment F u.se - i pp 52' '* ' pp 34434 Fu.N - n E pp 311 - 57G pp. 371-376 Husnan Factors tsoues. Date and Analyse's foe E PP 577-58i E PP 58 5'5 PP '"4 - ' ' 8 ggggggg teching esto the Data and Anetysis toe M 1NK Tutadal-t N tese Caticodiv Nu I.m Cenic.why MONet Tutenal-N MONE Tutenal-in 1990s - PeneJ S afety - 1 MONE Tue.. riel-tv saf.t y -It p 129 a se 1.5.127 pp ilu 1 a y til Concw Teesta no Advances in Off sete 3 p. 3 P E P 117 E e 18 '
by Radiat.on: Unc.rewnty Analysie ANs irrvolvement in the E , 4ccad no Consequence h Reactus safety Wiemote Repeacessing: The Use of Geographic A Geograph.c Informatio., Cuesent succeae. Anery.6e Waht Pvt,geern Feu.wsnet Dentosution Neuw Derwesopa.e.ese, informat.on suseems 6n syston Demonspott.no CAslNL T P, c..e Envoonmente8 Asseemment session \ .no Pusure Directions pp.49 )] g i Th. Use of Geograph6c wee.maunn s,meen.3 in pp 24 54 '- "' toe. guy Nesponse _E P' Pa 3 " - ' E pp. ze la FoRUu R nm.on avta.s in s- . m emingicea s niune in Bic ogical E. ** 6 5 * '"5 E
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- hism Pe.. to heu., satey pp 319-346 pp 24-27 g pp 270 279 y pp. 42 48 s.t.tv symma Funce..n.i Pt.no contor.none. vh E D' 3 7'- 3 9 pp. DwiL4al pn 246-2s i wepec no andsmers - se.kh.g anos.gy and Meduin.: Computee Appacetions.
COuut fitE Eme..: nosee.epe,ed g.ncy se Ost saa ess Gen it s.iect.d Tepace an E aceuonce in Plant Opwetiene i.oen toe imp <oving Pi.nu Op <etione Ef feciency in Opmations pp 496-102 pp 501-509 and u.in..n nc. g pp 310- 5:1 pp 6-14 pp $4-522 pp. S25-526 in -3. roolia.m. m rip. w.s Th nning et kwm Eau aewsag The ervects se Re9pi.dng F.e.,8 Managemoni and cech m utsA s klem Plwun Nethmaa Differm.ces on u.neg.m.no end D. sign and unint.nence ene Puhac Ae.c.pience Lue Edens on f hsence -l F mance - m Cons 4Jwenons in Curemn pp. 214-263 t wiewPc, . and Advanc.d Nece.s g pp 4i4 42 g pp 429 m g op. 'l'-*44 cDoesi raviron noni.i innpacte seon. Lic.e. sing he the Age E Pa *46-412 pp. en-419 po 477-4 tie Op .non en.s Di.p...I et Advances in Chemical Ut.hty Re.sadtehle. New Technoicgy en Plans et CAueno tapeas. wece es ope.eune h.cias o.c<,nt.n.n.non spe,. Pe.es New Technology in Piant space Nucl.se Powee Inha.a.gy s, stems:ca.npui send s v.t.me. we.;. ,uces G eanon pp 31 37 E histnum.nte.on r$ d24-42s g pp. 4 ti-ela p 443 g pp. 46a- 466 pp. 467 47a Menecament of "Mined WIPP Os.eestiomet Fue4 and Fud Cycles op 4s? 495 e n.a n s Westes" anJ Se.ew Rendaness and HLW Human Engineedng send Multigrid and Methods in Neut.at and _' R.u.*me.y Cene.,re foe Fase Reecuers Oposetos Pe.spectn as toe Ro ndtahle on Utskty ser Maheenatacel Modehng Chaeged Poetscle hanspost w.cosweem. rCaesu ecd.tv ceu.sy New Genweston hadweste Waste P.otdeiens pp 15 i.een,n.no vs uem, E '3 4' E **-7' a pp. s2.ss Thermet Hydraulics; Perfoemence Assessenent shippegpeet stunen a op. 290-io2 m op 3o1- > ! 4 e its a Genossa and Vandeteen Anesogs-1 Nucimee Fuel D. sign Fuel Cycle Management Packaging and DaGat D.comnwasianmg Progets and Analyses in Caes Fuel Econonues and Es.euemics Teenspoetetton of spene Fuel and pp 41% A27 pp 117-16S g pp 72-58 q pp. 59-92 pp. 91-402 tngh Level Wenee Bat an A Nucleos Waste Managemene MRS. LLW end Tea.nsporteten of Characterfastion of Tuff Chenecteeiration E ** 'oi ii2 e pp ii4 i2: e High level Weste stese Tuff Cherecteetserion Performance Assessm.nt Technology feenstw and in.ctsee Weste Acetwhles - t Actiwmee - Il pp 148-144 and Vehdeston Analous-N Quana, Assu.se.c. g pp.177- 61S g pp 186-192 g pp. 207-212 E pp 213-221 g op 166-176 op. 2 7s-245 spene F Fusion Energy. Gonees.4 m g EU4 RASE Conse.du.IRod s tnen and Reactor Plane R.nina. Meentes.ence pp MJ6 -404 pp 432 125 CAisFORNIA 1013 to il 41 A41 ps c,.,s.e . ] 11 Caafarna. FORUM
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9. 141 NUCLEAR WASTE MANAGEMENT Cosponsored by the isotopes and Radiation and the Fuel Cycle
- and Waste Management Divisions Session Organizer: J. C. Laul (PNL)
All Papers invited
- 1. Overview of the U.S. Program for Develop. House; directed the President to appoint a negotiator to seek ing a Wasto Disposal System for Spent Nuclear a state r Indian tnbe willing to host a repository or I uel and High.Lavel Waste, C. E. Ecy (DOE)
I*'*Y.at a suitable site and to negotiatetions terms and con & (including financial and mstitutional arrangernents) under which the state or tribe would be willing to host such a facil. ity; and amended, adjusted, or established other requirements Safe disposal of spent nuclear fuel ac eadioactive high-e ritained in the 1982 law. level waste (HLW) has been a matter of nauonal concern ever With these amendrnents, DOE's Office of Civilian Radio-since the first U.S. civihn nuclear reactor began generating active % aste Management began immediately preparing a cew electricity in 1957. Since then, electric utilities have accumu. , nussmn plan to reflect the changes in program direction and lated >l5 000 tonne of spent nuclear fuel. This spent fuel is to define the mformation needed. A site charactentation plan currently stored at the reactor sites.1here are >lM reactors consultation draft for Yucca Mountain was issued in January in 33 states licensed to operate in the United States and f Ilowed by techmcal workshops with Nevada and the U.S. approximately a dozen under construction and scheduled to Nuclear Regulatory Commission to discuss the contents of the come on line oves the next several years. Based on current munent and the characterization program described therein projections of commercial generating capacity, by the turn of the century, there will be >40000 tonne of spent fuel in the to be conduct:d at Yucca Mountam. After any appropnat,e changes are in:orporated in the site characterization plan, it United States will be issued to the public and public hearings will be held, In addit'on to comraercial spent fuel, defense MLW is gen. While the techrucal actmues proceed, the establishment on crated la the United States and currently stored at three U.S. the negotiator, technical review board, and the MRS co Department of Energy (DOE) cites: the Savannan River Plant sion are important elements an proceedingthsuccessMy m,mmis the (South Carolins), the Idaho National Engineering Laboratory developmcat of the naclear waste disposal system and should (Idaho), and the Hanford Reservation (Washington). Cumu-enhance the techrucal review process as we!! as communica-lative inventories of this defense HLW from 19% through the uons and interactions among affected and interested parties year 2020 is estimated to be the equivalent of -8000 tonne. In December 1982, the U.S. Congress took a major step and DOE. by passing legislation estabJsh; nit tu first cornprehensive U.S. policy for developitig a waste disposal system for spent nuclear fuel and HLW. Much progress was made over the 2. The Role of the Nuclear Re9ulato7 Com. ensuing 5 yr, while many institutionalissues were raised by mission 'n the Management of Nuclear Waste, members of Congress and affected and interested rsrtice . Hugh L. Thompson, Jr. (NRC) regarding the imp;ementat;on of the iluelear Waste Policy Act . of 1982 (P.L. 97-s25). With 35 pieces oflegislation proposed in general, the U.S. Nuclear Regulatory Commission within the first 9 months of the 100th Congress, it became (NRC)is responsible for reviewing and making licensing deci-clear that for the national program to proceed, adjustments sions to ensure that the U.S. Depaitment of Energy's (DOE's) to the national program might be necessary. high-level waste repository is designed, constructed, and oper. In December 1987, those adjustments were made in the ated without unreasonable iisk to public health and safety. In form of amendments to the 1982 hw. The Nuclear Waste implementing this responsibility, however, the commission's Policy Amendments Act of 1987 (P.L.100-203) provided for guidance to the staff is that, in the absence of unresolved financial incentives to bost a repository or a monitored retriev. safety concerns, the NRC regulatory program will not delay able storage (M RS) facility; mandated the areas m w hich DOE's the exec & oranch's program as set forth in the DOE project siting dforts (site characterization) should concentrate (Yucca decision schedule. Mountain, Nevada); required termination of site-spcific setiv. The NRC role for the next several years will be to develop ities at other sites (Hanford, Washicgton, and Deaf Struth its licensing framework and to consult with DOE on its plans. County, Texas); required a resiting process for an MRS facil. Consistent with the Nuclear Waste Policy Act of 1982, as ity, which DOE had protosed as an integral part of the waste amended in December 1987, we are working with DOE and disposal system; terminated att activities for identifying can- the state of Nevada to identify and resolve licensing issues at didates for a second repository; tstablished an Il-member an early stage to avoid delaying the licensing process. An Nuclear Waste Technical Review Board-members of which essentialingredient in the success of both NRC's and DOE's the National Academy of Sciences would nominate and the respective missions it the need for free and open exchange of President woulo appoint; established a tnree-member MRS information, which will assure us that the concerns of all par. commission to be appointed by heads of the U.S. Senate and ties are addressed.
/
142 Nuclear Waste Management With regard to low-level radioactive waste, the states have DOE is also working with these authorities to provide finan-the lead responsibility for disposal. This is primarily being cial assistance to mitigate the impact on the state of Nevada handled through the formation of regional compacts. As or affected units of local governments resulting from charac-directed by the Low-Level Radioactive Waste Policy Amend- terization of the site and, subsequently, development of a geo. ments Act. the NRC has developed its low-level waste facil- logic repository. ity licensing capability and guidance on alternatives to shallow in the area ofindependent oversight, the DOE is assisting, land burial and petitions to define waste below regulatcry con- as appropriate, the Nuclear Waste Technical Review Board in cern and is addressing disposal requirements for wastes & , the evaluations of the technical and scientific validity of the are greater than class C. The NRC also provides assistar7 ? site characterization activities and the packaging and transpor. the states and compacts on such items as regulatory pte h, tation of high-level wastes and spent fuel. Further, the DOE site characterization, and mixed waste disposal. is assisting, as appropriate, the Office of Nuclear Waste Nego. Another of the NRC's roles is in the managetuent of ura. tiator in its attempts to find a state or Indian tribe willing to nium mill tailings. The NRC has several responsibilities under host a repository at a technically qualified site on reasonabla the Uranium Mill Tailings Control Act of 1978. Under Title tenns. I of the Act, the NRC consults with DOE and concurs at key paints ia the cleanup process. The NRC will eventually license the long-term custody of reclaimed tailings. Under Title 11, the NRC or agrectnent state regulates the operation of the mills and long-term stabilization of the tailings. Currently, most of
- 4. Status of the NRC's High Level Waste twpository Licensing Prectam, Michael J. Bell the NRC's attendon is focused on ensuring adequate long-term stabilization of tailings. (NRC)
Under th e Energy Reorganization Act of 1974, as amended, and the Nuc! car Waste Policy Act (NWPA) of
- 3. The DOE Repository Program, Tom IsaacS 1982, as amended, the U.S. Nuclear Regulatory Commission (NRC) has the responsibility of licensing the repository to be (DOE) constructed and operated by the U.S. Department of Energy ne U.S. Department of Energy (DOE) has been directed (DOE) to dispose of the nation's radioactive high-level waste by the Congress in the Nuclear Waste Policy Amendments Act (HLW). At the present stage of the program, where a single (NWPAA) to characterize the Yucca Mountain, Nevada, site si.e has now been identified for detailed site characterization as the initial candidate site for the nation's first geologic prior to developing an application for construction authoriza-repository. Site characterization through ongo ng surface, tion, the interactions between NRC and DOE consist of in-based testing has been under way since the President approved forrnal prebcensing consultation. The NRC's prelicensing the recomrMation of the Yucca Mountain site as one of activities consist of two major cornponents: (a) development three cand:date sites in May 1986. of the body of regulations, guidance, staff positions, and A more extensive site characterization prograrr, including review plans that document for DOE and other interested par.
construction of exploratory shafts and an underground test; ties the requirements, procedures, and policies that NRC will ing facility, has been described in the consultative draft site apply io reviewing a license application; and (b) review of characterization pian (SCP-CD), which was provided to the DOE's site-specific plans, data, and analyses developed as part ' state of Nevada and the U.S. Nuclear Regulatory Commission of its site characterization program and providing comments (NRC)(Manuary 1983 for review and comment. In addition, on their adequacy to support a license application. tectuucal workshops were held with the state of Nevada, the Regulations under development by NRC include (a) a rule NRC, and their contractors in February and March to discuss that defines other highly radioactive materials requiring per-specific technical issues in the SCP-CD. manent isolation as HLW,(b) a rule that would specify the la the same time frame as the release of the SCP-CD, the criteria and procedures NRC would apply to adopt DOE's DOE laid out the design for its ens mmental program in environmental impac' statement, and (c) a rule that would plans for the environmental program, environmental regula- specify the criteria and frocedures for entering data into an tory corr.pliance, environmental morutoring and mitigation, electroniclicensing support systent, wMch would contain the and environrnental field activity. Similarly, the DOE issued information to oe relied on in the licensing hearing. Another its socioeconomic monitoring and mitigation plan in January rule to conform NRC's regulations to the Environmental Pro-1988, tection Agency's (EPA's) standards applicable to HLW dis. The consultative process for the SCP-CD, especially the posal is in abeyance pending EPA's resolution of a court technical workshops to discuss specific technicel issues and to decision remanding i s standard. INiew plans are being devel-facilitate state and NRC comments, should lead to release of oped to specify how the NRC staff will review DOE's site the site characterization plan for the Yucca Mountain site for characterization plans and qaa2y assurance (QA) programs. a formal 9(bday comment period and public hearings in late The QA nyiew phn (QARP) speci'les the way that NRC staff 1988, and, after consideration of comments, particularly those plan to apply the requirements of 10CFR50, Appendix B, and
. comments related to the construction of the exploratory shafts, the American Society of Mechanical Engineers,' NQA 1 the stad of shaft construction in June 1939. industry QA standard to site characterization activities at a The DOE was also directed by Congress in the NWPAA geologic repository. In the QARP, the NRC staff has impie-to terminate all site-specific activities at all other candidate mented many of the provisions of draft NQA.3, the industry sites, excluding reclamathn, within 90 days of enactment of consensus standard being developed for the HLW repository the NWPAA. Reclamation activities are under way at candL program.
date salt sites in Mississippi, Louisiana, Texas, and Utah and Ira its reviews of site. specific DOE plans and activities, the candidate brnit site in Washington. The DOE also ts NRC is reviewing trie NNWS1 Consultation Draft Site Char. phasing out research programs designed to evaluate the suita- acterization Plan, site study plans related to licersing matters, bility of crystalline rock as a potential repository host medium. and DOE programmatic QA documents in addition, NRC i The DOE has continued to make grants available to the starf are observing DOE investigations in the field and DOE state of Nevada and has implemented provisions of the QA sudits of contractor performance. Our objective at this l stage of the program is to provide suffic ent review and com. t NWPAA to include grants to affected local units of govern-ment for their participation in the repository program. The ment on DOE plans and data collection activities, including I i
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; l' E
6 Nuclear Waste Management 143 (y- QA measures being applied,in order to allow DOE te gather (OCRWM)is conducting a proactive institutional program to 3- inc information needed for its license appucation. complemeat technical developmant. External national profes-One final aspect of the NRC IILW program is also of sional organizatiora are being kvolved to resolv. a ~ ta-
, .nkrest. The NRC is in the process of getting its own techni. tion issues, su:h as state inspecti n standards anu 4 .ung i .:1 support program in sound order. The NRC has recently systems for any overweight shipments. Planning for facilities etablished a Center for Nuclear Waste Regulatory Analysis and procedures to manage and operate the future transporta-at the Southwest Research Institute in San Antonio, Texas, to tion system is also under way, provide the technical support that NRC will need over the The first cask development contract is scheduled to oc
,oming decades for the HLW repository program. T" con- awarded in February 1988. Four additional awards will be at:ctual arrangement provides a long. term source of mm_adis. made in the spring and summer of 1988. A comprehensive
, sioiinary technical capability that is free of conflict of interest. transportation plan is expected to be issued in draft form in i .Further, as a management strategy, the NRC staff has late 1988, which willinclude revisions to previous businass ed adopted a policy that the center's work must meet the same institutimal plans and will incorporate early plans fer oper.
QA criteria that the commission appUes to DOE and its cen- ating th. transportation system. trac 7rs. Tha NRC staff considers that this strategy will pro- Hirteen papers discussing identified transportation issues vice the commission with the high. quality technical support (e.g., touting, emergency response, inspection, and enforce-that it needs and willimprove its management of the contrac- ment) will be issued in early 1988 for public review and tor's programs. comment. A transportation meeting will be held the spring of 1988 to review the impacts of the new NWPAA on transportation planning. > 5. DOE's Storage, Transportation, and Sys-tems Integration Activities, Keith A. Klein Systems Integration
@ _ As part of the systems engincedag process, OCRWh1 sub-sa a y uma e a e manag e sys em requirements CURRENT STATUS OF PROGRAMS and description documert. which establishes the teference sys-Monitored Retrievable Storage Aethities tem and the development of the waste mansgement system. A coroputerized data base of thermal and rsaiological character-The Nuclear Waste Policy Amendments Act (NWPAA) of istics of spent fuel and high-level wast.s was established for 1987 annuued and revoked the U.S. Department of Energy's stagrated planning design and a .Wis.
(DOE's) proposal to locate a monitored retrievable storage To ensure that the reactors and the waste management sys-(MRS) facilicy m Tennessee. The same amendments authon2ed " tem are compatible with the transportation systems visits to the DOE to site, construct, and operate an MRS subject to specific conditions' reactor sites have been initiated to collect design - pera-
.. . tion interface data. Emphasis has been directed t - ard the An MRS review comrmssion appomted by Congress has develop nent of systems analysis capabilities that wul enable been established to study the reed for an MRS. After the MRS the assessment of alternative designs and operational p*uce.
commission's report to the Congress, the DOE may begin to dures. survey and evaluate potentially suitable sites. The most suit-able MRS site inay not be selected until the secretary of the STORAGE RESEARCH, DEVELOPMENT. AND DOE recommends the repository site to the President, fe,r DEMONSTRATION ACTIVITIES approval. Construction of the MRS may begin after repository construction is authorized by the commission. Construction or Dry Storage Modules operation of the MRS shall be prohibited if the repository Generic tesearch. development, and demonstration (RD&D) license is revoked or anstruction ceases. No more than 10000 of dry spent fuel m storage is under way tuat will provide data tonne U of scent fuel or waste may be stored at the MRS prior and informa6on for licensing of dry storage technologies. This to the receipt of waste at the repository. No more than 15WO nformation can be used to enhance at-reactor storage capac-tonne U may be stored at any time. ity. The DOE provided information from these RD&D activ-An Office of the Negotiator has been established in tne ities to the U.S. Nuclear Regulatory Cornmission while they executive office of the President. The negotiator is to reach a were establishing a"owable maximum temperature limits for proposed agreement between the United States and a poten-spent-fuel storage in inert atmospheres. tial host state and Indian tribe for an MRS site. The DOE may Other activities of the DOE cooperative RD1D dry stor-reake grants to states, Indian tribes, or local governmen:s to age program include cornpletion of testing of three different assess the heasibility of siting an MRS. When requested. the metal dry storage casks at Idaho National Engineering Lab-DOE shall prepare an environmental assessment of any site oratory (INEL), the fabrication for a dual-purpose transport that is the subject of negotiation. storage cask, and the licensing of a concrete horizontal module in the near term, DOE expects to develop MRS informa. storage facility. Development of both metal and concrete drv tion and materials and to perform specific studies and anal-storage casks is continuing under cooperative p: grams with yses on request to support the MRS review commission and selected utilities. the negotiator. Alternative MRS facility deplonnent strateg e will be investigar:d. The costt and impacts associated with these strategies will be further assessed, and alternative facility Protot?Pi cal Rod Conwlidation Development functional requirements will be developed. Wet consolidation demonstrations have been supported by DOE over the past few years. These include demonstrations Transportation Aethities by Rochester Gas and Electric Company at the Batte!!e Negotiations with cask developers are under way for legal Columbus Laboratories and by the Northeast Utilities Service weight truck and raiVbarge craks. Support actisity to resolve Company at their Millstone-2 reactor site, technicalissues related to cask development and cask testing A four-phased dry rod consolidation technology project programs is ongoing. mas conducted at (NEL to obtain spent. fuel assembly consoli-The Office of Civilian Radioactise Waste Management dation data. Phase I w as development of preliminary designs; m
/ 144 Nuclear Waste Management phase 2 is development and final design; phase 3 will be fab- and safety perspective, the nation's wastes could probably be rication and cold testing of the equipment; and phase 4 will disposed of properly with substantially fewer facilities. ff, as be hot testing of the equipment. Phase 2 of the Prototypical facility development continues, regional compacts and states Rod Consolidation Development Program should be com- wish to consider combining facilities to conserve resources, the pleted in February 1988 and phase 3 is scheduled to begin in NRC will be happy to assist them. May of 1988. The NRC responded to Congress' direction to develop the capt.bility to review and process a license application in 15 n, nths, in part, by publishing a Format and Content Guide (NUR FG-1199) and a Standard Review Plan (NUPEG-1200) 6, Low-Level Waste Management, Malcolm R. for a low-level waste disposal facility license application in Knepp (NRC) January 1987. The NRC also published a description of the license review process (NUREG 1274), which specifies the This paper reviews the U.S. Nuclear Regulatory Commis- skills and staff effort necessary to review an application. sion (NRC) staff views on three aspects of the Low Level Twenty-two disciplines and eight staff years are needd for the Radioactive Waste Policy Amendments Act of 1985 (the Act). review of the application alone. Additional time will be First, the Act confirmed that states are responsible for the safe t quired before receipt of the application to preside prelicens. disposal of classes A, B, and C low level waste and established ing guidance to the applicant and for staff familiarization with both incentives and penalties to encourage the formation of the site and i; sues. After completion of the review, resources regional corapacts for the development of low-level disposal will be needed for panicipation in any hearings that may facilities f or that purpose. Second, the Act directed the NRC, occur, De agreement states that will be regulating a low-level among other things, to develop the capability to review and waste disposal facihty will need to becorr'e familiar with these process an application within 15 months, and third, the Act needs and to act early to ensure that they have the skills nec-directed the NRC to develop guidance on alternative to shal- essary to act on a bcense applicatiort in a timely way. The NRC has chosen to !imit its guidance on .Iternatives low land burial. From the NRC staff's perspective, as of January 1988, the to shallow land burial to t vo alternatives to encourage stan-states' response to the Act is generally successful. Most dardization and to conserve resources. These alternatiscs are regional compacts and rtates appear to have met the Act's below-ground vaults and carth-mounded concrete bunkers. milestones on selection of a host state and submission of a rea- The ruidance is provided in revtsions to the Forrnat and Con-sonable site selection plan. These actions,if carried through tent Guide and Standard Review Plan completed in January to completion, would result in the creation of 13 or more new 1988. The revisions provide general and specific guida,ce for low-level waste disposal facihties, most of which are expected both materials and designs to ensure that the alternative will to be licensed by the states themselves under the NRC's agree- remain intact over the sescral hundred yea:s that low-levei ment state program. De NRC staff notes that, from a health vrastes wfil remain hazardous. B i t I i i l 1 i
4 166 PERFORMANCE ASSESSMENT AND VALIDATION ANALOGS-Il Cosponsored by the isotop$s and Radiation and the Fuel Cycle and Waste Management Divisions Session Organizer: Norm A. Eisenberg (DOE) M
- 1. Performance Assessments for the Safety activities that wiD be conducted for the evaluation of release Analysis Report, Donald H. Alexander (DOE), I the accessible environment include the foDowing:
Maxwell B. Blanchard (DOE, Las Vegas), Michael 1. identification of potentiaUy significant processes and D. Voegele (SAIC, Las Vegas), Larry D. Rickert. "cncs sen (IVESTON TST), invited 2. development of scenarios invohing those processes and events
- 1. ON
- 3. neening of the scenarios 6: cording to the probability The application for the license for the geologic repository of occurrence and the potential releases associated with system willinclude assessments of the performance of that sys- them tem. These assessments will be presented,in a safety analysis 4. development of appropriate conceptual and computa-report (SAR) and wiu mvolve an evaluation of the site, with tional models for the evaluation of the scenarios appropnate attenuon to those features of the site that might affect the abihty of the repository system to isolate the waste. 5. calculation of probability distributions for the cumula.
This paper describes the kind of performance assessments the tive rel:ase to the accessible environment. U.S. Department of Energy (DOE) expects to conduct for the The analyses to assess individual and groundw ater protection SAR and relates these assessments to the overall problem of are similar to these, in accordance with the regulations, how-issue resolution that is central to the DOE's efforts to charac- ever, the analyses wiu focus on anticipated processes and terize the site and to support the siting and beensing decisions events, that are to be made. The analyses of the effectiveness of engineered and natural barriers wiU be evaluated according to the performance ob. StJMMARY OF PERFOR. iANCE , jectives of 10CFR60.ll3, which include requirements on the ASSESSMENTS FOR Tile SAR containment by the waste packages, the rate of release of The specific performance assessments required for the radionuclides from the engineered barrier system, and the SAR must address the standards that are embodied in the groundwater travel tirne. Assessments of the containment by technical criteria of 10CFR60. In order to focus its efforts on waste packages will evaluate the foDowing: these technical criteria, the DOE has developed an issue reso- . . lution process ttiat includes the specification of the perfor- 1. radiau.on. cherm. cal, the mal, and fluid condit ons in the mance assessments that will be conducted. The set of analyses vicinity of the waste packages defined by this issue resolution process therefore compnses the 2. performance of the disposal container under these con-set of analyses for the assessment to be presented in the SAR, ditions The specific performance assessments that have been , defined include the following analyses: 3. release of radionuclides from the waste form, including any potential releases of volatile radionuclides.
- 1. release of radionuclides to the accessible environment, The auessment of the rate of release from the engineered assumics both anticipated and unanticipated processes g ,
gg yg an pents ues to be used in analyzine One waste package; (b) development
- 2. effectiveness of engineered and natural barriers impor. c.f geochemical modei., models for affecting radionuclide tant to waste isolation release, and models for assessing waste-package performance;
- 3. degree to which each of the favorable and potentia.Uy and (c) calculation of the rate of radionuclide release from the a ve e cen t ns p t at the site contributes to N w ast ac ar
,v evaluate the groundwater travel time include the following:
- 4. measures used to support the models used to perform the assessments in items 1. 2, snd 3. 1. development of conccptual and computational ground-water models The analyses under item I wiu be esaluated according to 7g gg ggg g the perforWnce objectises specified in 10CFR60.ll2, which groundwater flow caused by waste emplacement addresses release to the accessible environment, protection of individuals againt radiation, and groundwater protection. "Ihe 3. identification of paths of likely radionuclide travel
Performance Assessment and Validation Analogs-!! 167
- 4. calculation of the pre-waste emplacement groundwater These activities will present both radiological as well as travel time along the fastest path of likely ndionuclide nonradiological risks to the repository workers and the pub-travc; from the disturbed zone to the accessible envi- lic. Control of these risks is addressed in the OCRWM safety r ciment. plan. While control of radio:ogical risks is the primary ob-jective. DOE intends to consider both types of risk within an The analyses of favorable and potentially adserse site con- Integrated safety assessment framework to assure that efforts ditions will be evaluated according to the siting criteria of to reduce nsk m one area do not adversely impact another 10CFR60.122. The assessments will mvobe studies of the sen- area. Identification and control of risks will be supported by sitivity of predicted releases to the favorable and potentiaUy a safety assessment process. The results of the safety assess-adverse conditions et the site. rnents will be used to support consideration of preclosure De analyses of ,ncasures used to support the assessment nsks m the site selection process, to demonstrate compliance mod:Is willinvolve validation and verification of the models wno the applicable regulatory requiremene (10CFR60 and used in the analyses described above, including evaluation of 40CFR191 subpart A), to optimize the safety ard efficiency uncenainties in these models. Parameter uncertainty wu! be f the design,, and to develop public mformation on the safety addressed by taking parameter variations expucitly into ac- f the s count through stochastic modeling or by considering bound- y9 (o e safety analyses of the repository DOE is
-ing v Jues for parameters. Validation of conceptual models developing a preclosure risk assesunent methocology (PRAM) will involve (a) explicit treatment of alternative conceptual whose objective is to identify anci develop a consensus on the models, (b) estabi shing criteria for the validation and compar- analyt. cal procedures, cornputer codes, assumptions, and data iso,n of predictions with these criteria,(c) study of the sensi- bases to be used and to apply such methodology in address.
tmty of parameter values to uncertair. ties in the conceptual ,; g,y model and in the parameters, and (d) peer review by qualified The technical approach to assessment of public and occu-
- T'#* pational radiation exposures is to rely on methods and analyt.
*I I" ISSUE RESOLUTION AND CLOSl'RE used m.chniques that haveand the radiological assessment been developed licensing of other for and successfu:ly nuclear facilities. Assessments of exposures from routine oper-The performance assessments will be documented in a scries of issue resolution reports (IRRs), which will ',e used as ation will rely on standard techniques, such as those recom-the focus of discussions on the performance of the repository mended in 'J.S. Nuclear Regulatory Commission regulatory system among DOE, the U.S. Nuclear Regulatory Commis- guides and DOE orders. Assessments of exposures from acci-dents will emp!oy techniques of probabilistic risk assessment sior., and other reviewers. The positions regarding the regu.
in addition to deterministic. conservative methods of analysis. latory criteria of 10CFR60 that evolve from these discussions will thcn be formally presented in the SAR. The performance Assessment of nonradiological risks wiU prirnarily involve r.ssessments that serve as the basis for these positions wiU also review of historical data on risks from similar activities to identify potential risk contributors. The specific procedures for be presented i' the SAR, either in full or in summary with ref-erences to the IRRs. In this way, resolution of the issues asso- preclosure saf ety assessment of the repos. tory wiU be specified ciated with repository system performance can be documented in procedures guides developed under the PRAM program. cnd closed.
- 3. Current Issues in Postclosure Performance Assessment, N. A Eisenberg (DOE), A. E. Van
- 2. The DOE Approach to Preck,sure Reposi. Luik (PNL), B. Ross (Disposal Safety), invited tory S1fety Assessment, Check C. Eng (DOE),
David Michlewicz (WESTON TST), invited INTRODUCTION Performance assessment, a type of systematic safety anal. The Office of Civilian Radioactive Waste Management ysis, is a method (a} to predict the potential health, safety, (OCRWM) in the U.S. Department of Energy (DOE) is re- and environma:tal effects of creating and using a nuclear sponsible for the safe and permanent disposal of spent nuclest waste repository (b) to characterize these effects in terms of fuel and high level waste in a geologic repository. While the their magnitude and like!ihood, (c) to compare the character-primary focus of this effort is on isolation of the wastes from ization of these effects to standards of acceptability, and (d) the biosphere for thousands of years after closure of the re-to present the results of these analyses in a format useful to pository, DOE is also responsible for assuring that the public, regulators, scientists, and the public Postclosure performance repository workers, and the environment are adequately pro- assessment wculd thus be those analyses used to predict mined tected from the activities that will be carried out at the re- geologie disposal sys.em behavior after permanent closure. pository prior to its permanent closure. ~1he primary foce. of and motisation for performance as. The activities that will be conducted prior to repository sessment is to evaluate cornpliance of the repository with res-closure include the following: ulatory performance stan tards,8 although performance t assessments are expected to be usefulin guidmg and evaluating
- 1. construction of surface facib ies and subsur' ace exca- testmg, design, and site characterization actiuties.
vations As th; U.S. program moves into a period of site charac-
- 2. emplacement, including (a) receipt, handling, and prep- terization, two types of performance assessment activities are aranon of spent fuel and other wastes m surface facil' expected: improving performance assessment methods and ities for emplacement;(b) emplacement of wastes m the carrying out performance assessments. Analgical improve-ur.derground facihty, and (c) monitoring and tr'ainte' ments are expected to include (a) improved probabilistic and nance of activities before the repository is permanently deterministic modeling and (b) a substantial effort toward the closed salidation of nerforrnance assessment models. During the period of site characterizauon, performance assessments are
- 3. retneul operations, if required expected to be used to evaluate sue characterization activities,
- 4. decommissioning, includ ng the removal of the surface to guide additional characterizanon, to interpret and synthe-size field and laboratory data, and to determine when charac-faciliues anj the permanent sealing of ur.uerground tenzation appears sufficient to close out issues.
facElies,
163 Performance Assessment and Validation Analogs-ll DESCRIPTION OF THE WDRK 2. Proc. NEA Workshop Uncertainty Analysis for Perfor-Given that reduction af modehng uncertainty is an impor. '"#"##A " "'"'##M # # ' "# *#' tant aspect of Sotaining a license, a survey was made of pet. Organizadon for Economic Cooperation and Dnelopment, formance assessments for high level nuclear waste, mined Paris, France, IW, Mear Energy Agency. geologic repositories, and of the literature addressing the 3. N. A. EISENBERG, "Introductory Address," p. 32: R. M. major issues of performance assessment to identify potentially CRANWELL, F.. J. BONANO, "Sources / Treatment of significant, currently outstanding issues. The assessments Uncertainties in the Performance As>essment of Geolo;ie reviewed include those performed for the U.S. Department of Radioactive Waste Repositories," p. 53; R. M. CRAN-Energy (DOE), the U.S. Nuclesr Regulatory Commission, and WELL et al.,"Overview of the Treatment of Uncertamties ior a number of other nadonal programs. Particular attendon Arising in Radioacdve Waste Disposal Assessments," p.18, was paid to the statements of analysts regarding assumptions in Proc. NEA Workshop Uncertainty Analysisfor Perfor. made and the rationales given for those assumptions,if any. mance Assessments ofRadioactive lihrte DrsposalSystems, Attention was also focused on any sensitivity analyses or other OrFanization for Economic Cooperation and Dnelopment, indicators of the relatise importance of processes, parameters. Paris, France,1987, Nuclear Energy Agency. or esents. From this survey, a number of generally applicable issues were identified, each of which m turn contnbutes to the
- 4. B. ROSS "Disruption Scenarios for a High-Level Waste uncertainty in the results of the assessments. Given the direc- Repository at Yucca Mountain. Nevada." Waste Manage-tion that DOE received from Congress late m 1957, the issues ment 36, Vol. 2, p. 403, R. G. POST, Ed., Arizona Board related here are those either directly applicable to or suffi- of Regents (1936).
ciently general to be potentially applicable to a performance 5. N. A. EISFNBERO. A. E. Var LUlK, "Validation Activ-assessment of a Yucca Mountain, Nevada, repositury. ities Addressing Performance Assessment issues Pertinent to the U.S. DOE Geologic Repository Pro.iects," Paper 4.4, RESULTS Int. GEOVAL '87 Symp., Stockholm, Sweden. April 7-9, A recent workshop of the Nuclear Energy Agency on , car wer WeNm Wh uncertainty analysis in performance essessrrents2 concluded that, in executing postclosure performance assessments, uncer. tainty must be continually esaluated and must be evaluated 4. Performance Assessment Methodologies quantitatively wherever possible. There seemed to be agree, for the Analys.is of High-Lovel Nuclear Waste ment associated with the prediction of future states of nature Repositories, Evarisfo 1. Bonano, Roberf M. and their consequence.' A suney of work done to identify Cranwell, Paul A. Davis (SNL), invned possible future states at the Yucca Mountain location
- sus-gested that possible future events could be grouped into a rel- The Nuclear Waste Pohey Act of 1982 requires the U.S.
atively small number of scenario groups with similar effects. oclear Regulatory Commission (NRC) to evaluate a license Further evaluadon of those groupmgs,in terms of their likeli- ,pbeation submitted by the U.S. Department of Energy to hood of occurrence or their potential performance conse- ,:onstruct high-level nuclear waste (HLW) repositories. The quence, remains to be done. It seems likely, hcwever, that basis that NRC will use to determine the suitabihty of a poten-there will be few credible or meaningful scenarios that will tial HLW disposal site is the independent assessment of com-need to be closely evaluated for 19 Yucca Mountain repos- pliance with custire federal regulations. The regulations set it ory. forth in NRC rule 10CFR60 and in the U.S. Environmental The applicability of hydrologic now assumpdons has been Pretection Agency's standard 40CFR191 include criteria that questioned in a number of cases: the porous media approxi- must be met to ensure the effective long-term isolation of the mation for fractured hard-rock media or the use of Darcy w aste by the multiple-barrier system (repository and geologic flow equations in bedded salt modehng. A comparable issue formation) and to minimize the release of radioactivity to the at Yucca Mountain is the extent of unsaturated zone fracture accessible environment. Dow versus matrix-dominated Dows. Esaluatmg the possibihty Since 1976, the NRC has contracted to Sandia National and extent of unsaturated zone fractare now at Yucca Moun- Labora.ories (SNL)in Albuquerque, New Mexico, the devel-tain is important in addressing the regulatory requirement for opment of methodologies that the NRC will use to assess the preemplacement groundwater travel time. performance of HLW repositories. To date, SNL has devel-Radionuclide migration seems to be an issue typically oped two methodologies: one for bedded-salt formations' addressed through the use of distribution coefficients, al- and another for basalt formations.2 Work is currently under though one objection is that a model is needed that will ap- way to develop a methodology appbcable to welded-tuff for-proximate changes in solubihty and sorption and possibly mations. All three methodologies have identical structures colloidal transport conditions as a function of time and loca- because they address identical regulatory criteria. The main tion. Current analyses for Yucca Mountain use t solubihty- four components of these methodologies are (a) selection and l controlled source term and geologic layer specific sorp6on screening of series of e ents and processes (scenarios) that can l parameters along the flow paths in a system with oxidcus impact the release of radionucUdes from the repository and/or l conditions. the appropriateness and utibty of this paradigm their migration through the geosphere to the accessible envi-needs to be e aluated. In addition, the potential for colloidal tonrr ent, (b) mathematical models and associated computer or pseudo-colloidal transport mecharusms must be evaluated. codes to simulate the relevant physicochemical processes Addnional significant issues related to the unsaturated (meluding beat) for gisen scenanos and estimate their conse. l fractured rock at Yucca Mountain are the cuent and signifu quence, (c) probabibstic and statistical techruques for estimat-l cance of radionuchde transport in the gas phase ing overall risk and carrying out uncertainty and Sensitivity i A numtycr of other issues, from a variety of sources, hase analyses, and (d) procedures for using the models, codes, and ! been identified in the context of a possible iucca Mountain tecnniques in the methodologies. The differences in the meth-i repositor). Sorne of these issues have been hsted elsewhere.S odologies arise becaese the different propertes of the host I rnedium (e.g., bedded salt was considered a porous medium; i 1. U.S. Nuclear Replatory Commission. 10 CFR Part 60, basalt has fractored zones; and tuff is an unsaturated frac-I Disposal of High.Lesel Radioactne Waste in Geologic tured medium) require different inodels for simulating the l Reposuones," 46 FR 13980 (Feb. 25.1981) as amended in relevant physicochemical processes. l 45 FR 23194 Oune 21,1983), Federal Reprier (1987). An important aspect m the development of the SN1/NRC l l l l l
Perforrnanco Assessment and Validation Analogs-ll 169 meshodologies has been the demonstration of their use to ana- we summarize our mass transfer approach to making these hie HLW disposal at hypothetical sites. During the demon- predictions. uration, all components of the methodologies have been esercised. This paper describes the SNL/NRC performance FAR FIELD TRANSPORT anessmint methodologies. Specifically, it presents the man- Predicting the hydrogeologic transport of dissolved radio-cer in which the methodologies hase been developed, the par. nuclides to the environment is a problem of"far-field" trans-ticular regulatory critca that they address, and the manner pert. Most fhsion product nuclides migrate as single decaying m which the methodologies have been used in the regulatory species, but some actinides in spent fuci are members of long-process. Lessons have been learned from the demonstration of lived decay chains. Failure to account for the generation of sne bedded salt and basalt tnethodologies pertaining to (a) the daughter nuclides during traasport can lead to underestimating treatment of uncertainty in parameters and (b) sensitivity anal- cumulative releases or release rates. Chambr6 published ana-pis. Particular attention has focused on the inclusion of lytic solutions for tr e transport of decay chains of arbitrary uncertrinty in the boundary conditions for the groundwater length in three-dimensional flow fields in semi-infinite and flow modelin the vicinity of the repository and the impact finite porous media.8 The analytic solutions have been imple-that this uncertainty has on the estimation of specific perfor- mented as computer programs, and numencalillustrations are mance measures. The demonstration of the bedded-salt meth- given for chains of up to Ove members.3 These solutions and odology did not take into account this particular uncertainty. codes are far more general than others generally available.3 In this case, the groundwater flow on the regional scale was Analyses have been performed to predict dispersion-free trans. assumed to be known and not to be affected by uncertainty port in a steady, two-dimensional flow field and transport in in hydraulic parameters and scenarios that could occur on this a one-dimensional now field with a spatially dependent disper. scale. Hence, the boundary cond2tions for the flow field needed sion coefficient. Analytic solutions have also been devel-in the sitnula. ion of radionuclide transport w ere fixed; only the oped to predict transport in fractured media with diffusion edues of hydraulic, source term, and transport parameters into and out of the tock matrix, including the effect of par-were uncertain. The sensitivity analysis performed to identify allel multiple fractures.ts irnportant parameters was relatively straightforward. In the demonstration of the basalt methodology, the flow NEAR FrELD TRANSPORT boundary conditions required by the transport model were *Near field" transport is corcerned with the analysis of uncertin. These boundary conditions depended on the flow radionuclide mass transfer from waste rolids into groundwater field at the regional scale, which was allowed to vary due to and surroundmg rock. This provides the source term for far-uncertainty in parameters and/or due to potential future see- field calculations. hiass-transfer analysis in U.S. programs was natios. Consequently, the flow field in the vicinity of the stimulated when the National Research Councirs waste isola. repository was uncertain, Icading to multiple tsdionuclide Lion system study' questioned the assumptions tha' long-term trensport paths. The latter had a s:gnificant impact on the dissolution rates in a geologic repo:itory could be predicted estimation of groundwater travel times and radionuclide dis- from laboratory data on leach rates of waste samples. The charges to the accessible environment it also caused consid- actual processes of dissolution are reaction of the waste solid etable difficulties in the sensitivity analysis because of possible with groundwater at the waste surf ace and diffusion and discontinuities in the data. Two important issues are the ap- advection of the dissolved species from the surface into proach used in the demonstration of the basalt methodology groundwater in surrounding rock. Recognizing that the waste-to cirry out uncertainty snalysis for data and parameters and solid matrix and most of its solid constituents are of low solu-the propagation of this uncertainty to the estimate of perfor- oihry, we first sought an upper limit on the dissolution rate by mince measures, such as groundwater travel time and total assuming that the solution at the waste surface is saturated rtdionuclide discharges. with individual w tste constituents. Exact analytic solutions *" for the time-dependent mass-
- 1. R. M. CRANWELL, J. E. CAMPBELL, J. C. HELTON, transfer rate fiom a waste solid in contact with saturated R. L. IMAN, D. E. LONGSINE N. R. ORT!Z, O. E. porous ro.k showed that the limiting mass-transfer rates for RUNKLE, M. J. SHORTENCARIER,"Risk Methodol- the buried waste are so slow that the actual dissolution rate is ogy for Geologic Disposal of Radioactive Waste: Final expected to be limited by diffusive. convective transport in Report," S AND81 2573, NUREG/CR 2452, Sandia pores in the rock and not by chemical reaction at the waste National Labs. (1987). surface. For the low groundwater flows expected in U.S. re-p snwy pr grams, tne near4cM mass transfer from wane in
- 2. E. J. BONANO, P. A. DAVIS, L. R. SHIPERS,1. J.
HALL, K. F. BRINSTER, W. E. BEYELER, C. D. UP- * ****
- E.th txk p egeet" to be co- illed by molecular DEGRAFF, E. R SHEPHERD, L. M. TILTON, K. K. diffusion in the surrouncy media anc little affected by advect n. Another a .alysis used expenmental chernickl rmc.
WAHl. "Demonstration of a Peafctmance Assessmer.t ti n rate data as a boundary condition for the diffusion mase , Mcthodology for High. Level Radioactive Waste Disposal I' * ' ' " " * * * " " ** ** " "" '**" in Basalt Formations," SAND 86-2325, NUREG/CR-4759, during which the chemical 'eaction rate could control tne dis-Sindia National Labs. (to be published). solution rate. This time span is so short as to be unimportant for borosilicate glass, and this seems likely to be true also for spent fuel. These predictions were confintmd by a more recent gmeral analysis' of steady-state diffusive-advective mass
- 5. M:ss Transfer and Transport in Geologic transfer from a waste sphere that covers the entire range of RIpocitories- Analytical Studies and Appl.ica- groundwater flow. The near field analytic solutions have been tions, T. h. Pigford P. '.. Chambre, it'. It'-L. extended eho to include the effect of a backfilllayer between Lee (LBL), invi,,d waste solid and rockM' and the mass trarisfer of she hi hly soluble ecsium and iodine "cap" activity in spent fuel.gU8 Assessmg the long term performance of geologic reposi- These basic mass transfer equations and extensions for diffu-tories for radioactive waste requires rehable quanutative pre- sion-controlled release have been incorporated into Pacifie Northwest Laboratory's AREST code for predicting waste-dictions of rates of release of radionuclides from the waste into the rock, transport through the geologic media. cumula- form performance.
tne release to the accessible environment, and maximum con- Further extensions include analytic solutions for the effect centranons in groundwater and surfne water. In this paper, of repository heating on mass transfer of both low.solubihty
170_ Performance Assessment and Validation Analogs-ll and soluble species, mas the time-dependent diffusive release of these analytic tools have yet been utilited by the U.S. of radionuchde chains through backfillinto rock,22 the time- repository rojects. Such analytic tools have been used in the
; dependent diffusion of low-solubility species through backfill Canadian, Swedish,303' and Swisssa repository programs, into a rock fracture, and the time-dependent diffusive release Further analyses must address details, such as fracture net. . of low.solubihty species into porous rock matrix and rock works, release of gaseous species, nonuniformities in chemical fractures.28 De near field analyses are applicable to all re- environment, water flow in Mfill, transport asymmetries, pository projecM, including a repository in unsaturated tuff if layered roedia, unsaturated media, precipitation away from sediments or moist rock forms a diffusion pathway between waste surfaces, and transition from near field to far field waste packages and the tuff. transport.
Our studies of radionuclide releases from waste solids in a salt repository led to the expectation that, except for a short 1, P. L. CitAMBR1, T. H. PlGFORD, W. W.L LEE, J. time after waste emplacernent, releases will be control $d by AHN, S. KAJIWARA, C. L KIM, H. K!MURA. H. diffusive.adveedve mass t.1tnsfer into brine in grain boundaries LUNG, W. J. WILLIAMS, S. J. ZAVOSHY, "Mass of the consolidated salt sorrounding a waste package.2* Our Transfer and Transport in a Geologic Environment "
; analyses of the time-dependent rnigradon of grain boundary LBL-194.30 Lawrence Berkeley Labs. (198f).
- brine after consolidation 2s can be used to predict the transi:nt advection by bdne in salt, w hich may be so small as to be neg-
- 2. H. C. LUNG, P. L. CHAMBR8,'T, H. PlGFORD, ligible compared to mass transfer by molecular diffusion. W. W L LEE, "Transport of Radioactive Decay Chuns in Finite and Semi-infinite Porous Media," LBL-23987, Examples of diffgsion calculations of release rates into salt Lawrence Berkeley Labs. (1987).
have been given. The equadons for transient release from was'e packages into a rock fracture can be applied to waste 3. A. B. GUREGHIAN, "Analytical Solutions for Mul. packages intersecting nonbalite interbeds in a salt repository. tidimensional Transport of a Four Member Radionuclide Decay Chain in Ground Water," BMI/OCRD-25, Battelle INTERMEDIATE-FIELD TRANSPORT Memorial Institute (1987).
"Intermediaw-field" transport concerns radionuclide mi. 4. D. K. TING, P. L CHAMBR1, T. H. PlGFORD, *Ra-gration from arrays of discrete waste packages. Our analyde dionuclide Migradon in a Two-Dimensional Flow Field,"
solutions5 2" of the multidimensional advective transport Trans. Am. NucL Soc., 39, 176 (1981). from waste package arrays show a near region in which the
- 5. T. H. PlGFORD, P. L CHAMBR1, M. ALBERT, M.
concentrations vary greatly in the direction transverse to FOGLIA, M. HARADA, F. IWAMOTO, T KANK!, D. groundwater flow, en intermediate regiun in which the array LEUNG, S. MASUDA, S. MURAOKA, D. TING, *Mi-can be treated u an infinite plane source of dissolving species, and a far. field region in which the array can be treated as a gration of Radionuclides Through Sorbing Media: Ana. plane source of fimte extent. The array equations have been 1 Sol doMI,"LBL ll616. Lawtence Berkeley Labs. developed for both porous and fractured media. These in. @BO). termediate-field ar alyses will be useful to repository projects 6. C. H. KANG, P. L CHAMBR8, T. H. PlGFORD, in making detailed predictions of releases to the environment. "One Dimensional Advective Transport with Variable Dispersion," Trans. Am. NucL Soc., 50, 140 (1985). MMA
- 7. J. AHN, P. L CHAMBR1, T. H. PlGFORD, %cSde An extensive body of analytic mass-transfer theory exists Migration Through a Planar Fissurs with Matrix Diffu-to predict the isolation perforrnance of geologic repositories, sion," LBL-19429, Lawrence Berkeley Labs. (1985).
Special features of analytic solutions for this application 8. J. AHN P. L CHAMBR$. T. H. PIGFORD,"Radio-include the following: nuclide Migration Through Fractured Rock: Effect of
- 1. Analytic solutions are compact. It is easier to obtain Muldple Ftactures and Two-Member Decay Chains,"
insight and predict trends from analytic solutions than from LBL-21121, Lawrence Berkeley Labs. (1985). reams of numerical calculatioct 9. T. H. PlGFORD, J. O. BLOMEKE, T. L BREKKE,
- 2. By the use of scaling and dimensionless groups, it is G. A. COWAN, W. E. FALCONER, N. J. GRANT, possible to obtain results applicable to many nuchdes by a sin. J. R. JOHNSON, J. M. MATUSEK, R. R. PARIZEK, gle computer run, instead of having to make multiple ruas R. L. PlGFORD, D. E. WHITE, A Study of the Isola-with numerical codes. toon System for Geologic Dssposal of Radioactive Wastes,
- 3. Most analytic solutions are more economical to imple-adnMA my hess. Washgton, M. 0%
rnent and run as computei todes. 10. P. L. CHAMBR8, T. H. PlGFORD, Y. SATO, A. FU. JITA, H. LUNG, S. ZAVOSHY, R. KOBAYASHI,
- 4. Analytic solutioris have been used extensively in the ver.
"Analytic Pe<formance Models," LBL 14842, Lawrence ifica Jon of numerical codes.
Berkeley Labs. (1982).
- 5. Analytic solutions are the best means of determining mathematical hmits of the fundamental theories used for per-
- 11. P. L CHAMBRt. T. H. PlGFORD, S. J. ZAVOSHY, "Solubility-Limited Dissolution Rate in Groundwater,"
formance prediction. T An Nuch Soc., 40, 153 (1982).
- 6. Analytic solutions are the best means of designing ex.
- 12. S. J. ZAVOSHY, P. L CHAMBR8, T. H. PlGFORD, pe,iments to vahdate predictise theories.
"Mass Transfer in a Geologic Environment," Scient(Sc
- 7. Analytic solutions can sometimes yield exact solutions Bansfor Nuclear Waste Management, Vol. Vllt, p. 311, that are difficult to obtain otherwise, such as advective trans- C. M. J ANTZEN, J. A. STONE, R. C. EWING, Eds.,
port without dispersion. Materials Research Society, Pittsburgh, Pennsylvania A bmitation of analyuc solutions is that it is sometimes U not feaele to obtam analytic solutions for problems involving 13. P. L. CHAMBR8, C. H. KANG, W. W L LEE. T. H. complics;ed and detailed geometries, such as for radionuclide PIGFORD, "The Role of Chemical Reaction in Wasie-transport across intersecting fractures. Only a hmited number Form Performance," Scientific Basis for Nuc/ car Wasic
9 Performance Assessment and Validation Analogs-ll 171 Monatement, Vol. XI, M. J. APTED, R. E. WESTER. 30.1. NERETNIEKS,"Transport of Oxidants and Radionu. MAN, Eds., Material Research Society, Pittsburgh, Penn- clides Through a Clay Barrier," KBS TR-79 (Feb.1978), sylv:.nia (1988). 31.1. NERETNIEKS,
- Migration Model for the Near Field,
- 14. P. L. CHAMBR2, H. C. LUNG, T. H. PIGFORD, Final Report," Report KBS 82-14 (1982).
"Mass Transport from a Waste Emplaced in Backfill and Rock," Trans. A m. Nucl. Soc., 44, ll2 (1983). 32. R. J. HOPKIRK, D. J. GILBY, W. H. WAGNER,
- 15. P. L CHAMBR$ T. H. PIGFORD, "Predictions of "Modelling of Solute Transport in the Near Field of a Waste Performance in a Geologic Repository," Scientific High Level Waste Repository," Report 85 25, Pc'y-Basisfor Nuclear Waste Management, Vol. Vll, p. 985, dynwics Ltd. Zurich (1986).
G. L McVAY, Ed., Materials Research Society, Pitts-burgh, Pennsylvania (1983).
- 16. H C. LUNG, P. L CHAMBR8, T. H. PlGFORD, 6. Comparison of Source Term Calculations W. W-L LFE,"Transport of Radioactive Decay Chains Using the AREST and SYVAC-Vault Models, in Finite and Semi-Infinite Porous Media," LBL 23937, M. J. Apted, D. W. Engel(PNL), N. C. Garisto, Lawrence Berkeley Labs. (1987)- D. M. LeNeveu (AECL Whiteshell-Canada) 17,' C. L KIM, P. L CHAMBR$. T. H. P!GFORD, "Mass.
Transfer Limited Release of a Soluble Waste Species," LNTRODUCTION Trans. Am. Nucl. Soc., $2, 80 (l986). A key supporting step in the validau.on of performance
- 18. P. L CHAMBR1, C. H. KANG, W. W.L LEE, T. H. assessment codes for nuclear waste disposal is to compare ver-P!GFORD, "Mass Transfer of Soluble Species into Back. ified codes developed for similar analyses. In this paper, we fill and Rock," Trans. Am. Nucl. Soc., 53, 136 (1986). report on the first such comparison of system. level codes for
- 19. A. M. LIEBETRAU, M. J. APTED, D. W. ENGEL, waste package performance assessment, specifically compar-M. K. AL'i ENHOFEN, C; R. REID, D. M. STRACH, ison of release calculations by the AREST and SYVAC Vault models (SYM). The purpose of this comparison is to further AN, R. L ERIKSON, K.1. JOHNSON, "ne Analnical establish the scientific credibility of these codes for use m Repository Source-Term (AREST) Model: Description and Documentation," PNL-6346 Pacific Northwest Lab. Predictive assessment of radionuclide release, as well as to identify deficiencies and future improvements.
{j 937),
- 20. P. L CHAMBRn, W. J. WILLIAMS, C. L KIM, T. H. PROBLEM DEFINITION PIGFORD,"Time Temperature Dissolution and Radio-nuclide Transport," Trans. Am. Nucl. Soc.,46,131 (1984). Both SVM (Ref.1) and AREST (Ref. 2) are system-level codes that are being developed to predict the long-term con-
- 21. C.L KIM, W. B. LIGHT, P. L CHAMBRf, W. W.L. tainment and controlled release of nuclear waste from a large LEE, T. H. PIGFORD, "Variable Temperature Effects array f nste packages ernplaced m a deep geologic reposi-on Release Rates of Readily Soluble Nuclides " UCB- t ry. The determhistic processes af fecting the release frorn the
'NE-4115, LBL 24805A, Lawrence Berkeley Labs $ (1983). waste package that are modeled include rate of containment 22, P. L CHAMBRt. H. C. LUNG, T. H. PIGFORD, failure, waste form release / dissolution, diffusive / convective "Mass Transfer of a Radioactive Chain Through Back- transport, sorption, radioactive decay, and precipitation. For fill," Trans. Am. Nucl. Soc., 52, 78 (1986), source-term calculations, mass transfer models describe the site- and design-specific release of nuclides from the waste
- 23. J. AHN, P. L CHAMBRf, T. H. PlGFORD, "Tran- fwm, uanspat thing imuve sient Diffusion from a Waste Solid into Fractured Porous packing, buffers), and mto release the host,ning engineered rock. The SVM barriers (e.g.,
Rock'* Trans. Am. Nucl. Soc.' 56' 173 (1988). and AREST codes are structured for stochastic sampling of
- 24. T. H. PlGFORD, P. L CHAMBRf. "Mass Transfer in parameter distributions and presentation of results in a prob-a Salt Repository," LBL-19918, Lawrence Berkeley Labs, abilistic format.
(1985). There are several differences between the SYM and A T co
- 25. Y. HWANO, P. L CHAMBRn W. W L LEE, T. H. ge metry,,da. De SW s that waste code package sohn designs mustmass uansfu fw a plane be converted PlGFORD, "Pressure induced Brine Migration Within t a senn d en m s. A e e h based a Consolidated Salt in a Repository *" Trans. Am. Nucl. ana ca mass uansfer epades fm a sMeal geom @
Soc., 55,132 (19873* which the spherical surface area of the waste form is equal to
- 26. P. L CHAMBRn, Y. HWANG, W. W-L. LEE, T. H. the surface area of the actual cylindrical waste container.
P!GFORD,"Release Rates from Waste Packages in a Salt A Canadian conceptual design for a waste packagel was Repository," Trans. Am. Nucl. Soc., 55, 134 (1987). selected for this comparison, with spent fuel as a waste form and a packing (buffer) between waste container and host rock.
- 27. C. L KlM, P. L. CHAMBR1, W. W-L LEE. T. H. * * * " ' " * ****"# * " * * * "' ### #"'** **
PlGFORD,"Radionuclide Transport from an Array of ' pdon Mdents wue tab fran Wera-Waste Packages in a Geologic Repository," Trans. ,4m. g, " , ' s,
- Nucl. Soc., 54, 109 (1987),
- 28. J. AHN, P. L CHAMBR8, T. H. P!GFORD, W. W L RESULTS AND CONCLUSION 5 LEE, "Radionuclide Dispersion from Multiple Patch Mguro a and 2 show a comparison of radionuclide release Sources into a Rock Fracture," LBL 23425, Lawrence rates for the entire repository (R.,, in moles per year) versus Berkeley Labs. (1987). time after release (r,,, in years), calculated from the SYM
- 29. N. C. GARISTO D. M. LeNEVEU,"A Vault Mudel for and AREST codes for a repository containing 1.91 x 10 8 the Assessment of Used Fuel Disposalin Cariada," Scien. tonne U of spent fuet Nuclides released from the UO: matrix tt4c Barafor Nuclear li'aste Management, Vol. XI. M. J. of spent fuel are shown in Rg, L Figure 2 presents results for APTED. R. E. WESTERMAN, Eds. (1958). inventory-limited ("instant") release for the repository of sol-
172 Performance Assessment and Validation Analogs-li 2- _4- . l .,
-6' .
/
j
................U-238 t>. -8'
'- ~ 1......
./ .
PU-242
-10' O
l
- h. . ' ', ' U'23*
' . . . . . . . . . .p u - 2 4 2 -
d ' I_ ce N..,,,,,,,,, - 3 -14
..,0 234 l
-10' ,
l ', l .ta-230 n-230
-18' i- i i , i i 2 3 4 s s 7 Log to (yrs)
Fig.1. Comparison of calculated release rates for matrix nuclides by the AREST and SVM models. SoUd hnes show AREST results; broken bnes show SVM results. 2' l . 1- *,* ll '.'. ll '.'. O' ll '.'.
; \'., *,
oo . a .
-l' ll
,, ll '.' . ^ ' . '.
K , ,% ..N., N ,
,' l l '., .,
o ,',,
- l '., . '.
O g , _3 - , , , , / i !-129 - l N. . ic-99 5 [ _4- . . , ,' ' ,\ (5-135 3 , l ' ' \'.' .
-G- / i *. .
./ '.
' N. .1-129
'., \.y . 9 9 t s -13 5
-7 , , , , , ,
2 3 4 5 6 7 Log t, (yrs)
' Fig. 2. Companson of calculated release rates for Fap nuchdes by the AREST and SVM models. Solid lines show AREST results; broken hnes show SVM results.
uble nuclides Icented in the gap region between the UO2 Food agreement (within a factor of ~10), with identical rei. 5 matrix and cladding of spent fuel. ative positions of release rates curves. After 10 yr. tne calcu. At times less than 1000 yt. the AREST code predicts lated results from the SVM fall off more rapidly than those higher nuclide relea.e rates from the UO matrix than does from the AREST code. Tnis is attributable to differences in the SYM code. This is attributable to the different techniques planar and sphencal geometries and to the hmited thickness for samphng from distributions of containment failures, of host rock used in the SVM code compared to the semi. Between 103 and 10' yr. the results from the two codes are in infirute host rock bcundary condnion used in the AREST
- . 1 P:rform:nca A:se:sm:nt cnd Vclid:ti:n An:l:gs-ll 173 m code. A f"mite-thickness host rock in planar geornetry leads to y La pseudo steady state release at long times due to radioactive decay.
X There is fair agreement between the results for the inven. ""*" tory limited release of "Tc and St. The SVM values are ini-
- : ally higher than AREST results; bes*een 10 and 10' yr, 8
* / j
~ SVM results are lower by a factor of 100. The '"Cs release ,
rate c"Iculated with SVM is a factor of 100 higher than tu A5,mW //g
' AREST results, attributable to the difference in geometries aid the effect of a finite thickness of host rock. Addidonal g * * *
- j/
Sensitivity studies on the effects of sorpdon, decay constants, f ## "
' and boundary conditions are being conducted to better under.
stand these comparative results. pg p.) Z
--l. D. M. LeNEVEU, "Vault Submodel for the becond somy4=teo a D"**
inttrim Assessment of the Canadian Concept for Nuclear co<cenvano W ,-N -- Fuel Waste Disposal: Post-Closure Phase," AECL-8383, Atomic Energy of Canada, Ltd., Whiteshell Nuclear Re-p " search Establishment, Pinawa, Manitoba, Canada (1986). { O r a & "
% Fractm '
- 2. M. J.- APTED, A. M. LIEBETRAU, D, W. ENGEL, g
- s "Spent Fuel as a Waste Form: Analysis with the AREST w,,,,
Performance Assessment Code," Waste Afanagement '87, Roch gia
- p. 545, R. G. POST, Fd., Arizona Board of Regents ,...-s (1987).
- 3. N. C. GARISTO, F. OAR:STO,"The Effect of Precipi. ggg tation on the Long Term Release of Radionuclides from Used Fuel," Ann. Nucl. Energy, 13, //, 591 (1986). Fig.1. Comparison of (a) planar geometry, used in other studies, and (b)(ylindrical geometry, used in this study.
- 7 Tr:nsient Diffusion from a Waste Solid into _
Fr:ctur:d Porous Rock, J Ahn, P. L. Chambr/' centrations are normalized to the quantityjo defined in Fig. 2. T. H. Pigford (LBL) The mass Dux into the fracture is c Jeulated to be about two orders of magnitude greater than that into the rock matrix, Previous analytical studies of the advective transport of because of the assumed hundredfold greater poro:ity in the dissobed contaminants through fractured rock have empba- fracture. sized the cf feet of molecular diffusion in the rock matrix in Figure 3 presents release rates as a function ar time after affecting the space-time-dependent concentration of the con- beginning of dissolution, calculated by integrating the time-taminant as it moves along the fracture.8-4 Ma'rix diffusion dependent mass flux over the waste surface. The mass release only in the direction normal to the fracture surface was as- rates are normalized to the quanuty draDN', where or is the sumed. Contammant sources were constant concentration sur- cylNder radius. Even though the mass flux from the waste into faces of width equal to the fracture aperture and of finite or the rock matrix is low relative to that into the fracture, the infmite extent in the transverse direction, es shown in Lg. It larger waste surface exposed to the matrix and the greater Such studies illustrate the far-field transport features of frac- assumed matrix sorption result in greater release rate to the tured media. To predict the time-dependent mass transfer matrix than to the fracture. This indicates that, for the param-from a lon.e waste cylinder surrounded by porous rock and eters assumed here, the earlier mass-transfer theonc/ tov a intersected by a fracture, the present study includes diffusion waste solid completely surrounded by porous ut.itactured rock from the waste surface directly into porous rock, as well as the can adequately predict release rates in low-flow conditions in more re:.listic geometry shown in Fig. Ib. Here we present fractured toedia. If tortuosity significantly reduces the diffu. numerical results from Chambr& analytical solution fer the sion coefficient in the rock matrix and not in the fracture, time-dependent mass transfer from the cylinder for the low- mass transfer directly from the waste to the fracture becomes flow conditions wherein near-field mass transfer is expected it ; we t, to be controlled by molecular diffusion.' The governing equations describe three-dimensional dif-iusion in the rock matrix and two-dimensional diffusion in the 1.1. NEP.ETNIEKS, "Diffusion in the Rock Matrix. An fracture. assuming local sorption equilibrium and uniform Important Facter in Radionuclide Retardation?" J. Geo-concentretion across the fracture width. A constant concen- phys. Res., 85(B8) (1980). tretion N* of low solubility dissolved species is prescribed at ! aste surface. No waste container is present. The solution 2. D. H. TANO, E. O. FRIND, E. A. SUDICKY, "Contami-aes to an infmitely long cylinder of constant radius and is nent Transport in Fractured Porous Media: Analytical
.ood tpproximador fcr a long cylinder with negligible end Solution for a Single Fracture,* Water Resourcer Res.,17, effens. A nonzero steady-state solution exists for species with 555 (1981),
tsdiocetive decay. The results are illustrated in Fig. 2, which shows instantaneous concentration isopleths, mass flux across 3. P. L. CHAMBRf! T. H. PM OAD, i. SATO, A. FU. the fracture surface, and mass fluxes from the waste into the JITA, H. LUNG, S. 7MOSHY, R. KOBAYASHl. fracture and into the rock matrix. The diffusion coefficient D "Analytical Performance Models," LBL 14842, Lawrence is conservatively chosen as that for a liquid continuum. Con- Berkeley Labs. (1982). ,
7--- d
^ 174 Performance Assessment and Validation Analogs-ll 1
qi i i1 6 a 1 l 2n Pu l (Halilife : 24,400 yr) Normalized flux from Cyhncer radius, a = 25 cm cyhncer to fracture. E E Fracture width,2b = 1 cm . f,(t4 .. 1o-1_ j 3 Porosity of fracture, c3 = 1 > C' Porosity of rock, c2 = 0.01. . . _ / fj, Retardation factor in fracture, K, = 1 jg Retardaten factor in rock, K2
- 500 y 10-8 ga Diffusion coefficient D i = D2
- D / j3
=500 crn2 /yr (b) y Solubihty-kmited c.cncentration, N'
, ,,,,,,,, 10-8 N
- Da N' AMt y l At 625 vsar l '
4,/#4##' (c)
/
/ /W J _ar E 10-8 g CE C lf43
=t 10-4
[~
# ' /[ ~
- , a.Eg 5EE D W / /
2*!v / /p
)#3 o
10.s (a) 3p / //////// 7
/ //
Act.tceJzwatMfat22rr 49n:ktemmrftstftst)dzw ret 2ii$ / Fig. 2. Illustration of nuclide migration at 625 yr: (a)isopleths of normalized concentrations in fracture and in rock, (b) not. malized flux from waste cylinder to rock, and (c) normalized flux from fracture to rock. 101 i e i e i 4 J. AHN, P. L. CHAMBR1, T. H. PIGFORD, "Radio-nuclide Migration Throu2h Fractured Rock: Effect of Z
~: . Multiple Fractures and Two-Member Decay Chains,"
j j , _ , _ _ y" ": LBL 21121, Lawsence Berkeley Labs. (1985). I am mgM i 5. P. L. CHAMBR$, T. H. PIGFORD, "Predictions of 41 - - Wane Performance in a Geologic Repository," Scientuic
*E Y '
~~: - m Basisfor Nuclear Wa:te Management Vol. V11, p. 985, f ,
M em G. L. McVAY Ed., Elsevier, New York (1983). 2 . 241Am k .
.. E --
- 8. Systems Approach M Developing and j10 %a '%.'l,"'"""
- Implementing an HLW Licensing Process, R.
t ~~. 239fu Adler, IV. Patrick, A. IVisiting (CNIVRA), invited 2 ~ % ". .s. .... I 9 '-\.._ INTRODUCTION
$ v2 Q Developing and licensing a repository for the disposal of high-level nuclear waste (HLW)is an important national goal g g, Congress reaffirmed this goal by the passage of the Nuclear
' ' ' ' ' Waste Policy Amendments Act (NWPAA)in December 1937.
1 10 102 303 104 gos 106 In addition to designating Yucca Mountain in Nevada as the le site i unders characterization, it authorized a moruiored Time, vears - retrievable storage f acihty (MRS) and created a negotiator, a Fig. 3. Normalized release rates of nuclides from a 3-m.high technical review board, and other entities whose efforts are waste cyhnder. Parameters from Fig. 2 apply, directed to provide greater certainty in the nation's ability to
1 Performance Assessment and Validation Analogs-II 175 mor: age its HLW. Responsibility for the formal licensing pro- oping a systems approach to implement and streamline the cess for the life of the repository is assigned by law to the U.S. HLW licensing process. This paper describes the basic systems Nuclear Regulatory Comreinica (NRC). .. approach and the design process and provides a status on the in October of 1987, the NRC estab'ished the Center for initial efforts of the center to develop this system. Nuclear Waste Regulatory Analysis as a federally funded research and development center to assist in fulfilling its licen5" SYSTEMS APPROACH AND PROCESS ing mission with regard to HLW. The broad objective of the center is to assist the NRC in identifying and recommending The HLW bcensing process is technically and administra.
- solutions for technical, regulatory, and institutional uncertain, tively complex and sophisticated, in addition to requiring a ties to ensure timely and credible completion of the licensing formal administrative law procedure for life-cycle licensing process. To meet this objective, the center is currently devel, and a multiple. party evaluation and approval prucess involv.
i
-.3 , 3 .idecktifyb a 1 13.Specify Alternate kAhilesbie Stat'utes '; . Programs & Changes to _
'+ c & RegWations b Reduce Critical Uncertaintles f
- 2. Analyze
- 14. Develop Costs, Regulatory Schedules, Lead Times, Requirements _
genefits & Risits for i Each Alternate Program { > 4. Describe /
- 3. identify / Categorize _.,,,
; Ouantify > 4
. Regulatoryl . . .
f Required Find ogs & lttsututional W:15; Analyre J.. t Uncertalnties 1 Program Trade. ohs s
, f 5.loentifyI h
.., ' int errelationships i . ;16.' Recommend M
' Among Waste Systems ,Uncertalnty Reduction Cornponents & Fbdings drograms, Changes & $
Research Programs O h
~
Inform tion equired /1h Dlh$y Netviork' Technical M Finding Uncertainties ' & Critical Patte . . Each @ ng\ ' e-- .[ SIIdentifyl, , f J Capabilities for , /18. Display Total W I . Processing information g.c ogramr for EachR - f 7Findtng; n,
- 9. Develop & Prioritize h Costs, Schedules, & Lead 19.DEument Prog'rerns T;mes to Obtain Required Structure & Changesy info. & Capabititles i
h 1 - j
-10. consolidate & Rank
- m. issue-l : ' AllUncertainties e Emlutlon-J l t
Affecting Finding l 11. Obtain DOE [
] Information j l Requirements & g POINTS IN THE PROCESS REQUtRING ! l INTEGR ATIOH OF INFORMATION l A
[ FROM ALL PROGRAM ELEMENT AREAS 12. Obtain inf o. l ' I g Requirements & Uncertainties I
! of States 1ndian l
! Tribes & Others l 3 I t_______.____a Fig.1. Process diagram for developing and maintaining the program architecture.
176 - Performance Assessment and Validation Analogs-ll
- ing many institutions, the entire system wiU be under public process, inputs from the program elements are reviewed and scrutiny. The NWPAA requires that NRC review the license integrated at a systems level to ehminate redundancy, estab-application within 3 yr of receipt. Furthermore, licensing lish priorities, and provide a basis for development of system approaches to date have focused on bt:t one subsystem of the alternatives. As they are developed, the results are compared HLW management system: the med geoingic repository. All to the reference system design requirements.
of these factors coc. tribute to producing a high-risk HLW licensing system. In order to achieve a credible and efficient CONCLUSION licensing process, these risks must be recognized, controlled, By August of 1988, the specification for the final design will be completed and a first-stage prototype system to reduce Thec ter is using a "top-down" systems engineering ap- the risk in the licensing process will be developed using the sys-proach that is mission oriented, requirements based, proactive, tems approach and systems engineering techruques described integrated, and dynamic. This approach will result in the de- here. Successfulimplementation of this systems approach to vdopment and implementation of a beensing system that will, the HLW licensing process wdi provide the fouowing results:
' in a timely manner, identify and provide alternative solutions to technical, regulatory, and institutional issues and unecrtain- 1. reduce schedule risks through (a) comprehensive eval.
ties (both inconsistencies and poicts of contention), in many uation of programmatic requirements and uncertainties, cases prior to submission of the initial license application. (b) carly identification of problems and issues, (c) important aspects of this approach are its inclusion of the proactive resolution of issues, and (d) streamlining the entire HLW management system [ mined geologic repository, licensing process at reactor storage, defense high-level waste, West Valley wastes' 2. conserve resources through (a) focusing on the NRC. MRS, tranrportation, and ahernative programs (if developed)] HLW mission, (b) prioritization of actions, (c) inclusion and its treatment of the entire life cycle of the repository of only essential program clements, and (d) integration. (construction authorization, operationa8 beense, operational both programrnatically and organizationally monitoring, closure and decomebsioning, and postclosure monitoring). 3. increase public confidence through (a) objective evi-A reference system design concept has been conceived dence that a DOE license appbeation is being processed based on regulatory requirements, required finings, and iden- in a timely manner, (b) a comprehensive basis for tification and resolution ofissues. The process of developing license review that includes all regulatory requirements, the system description, referred to as the "program architec. and (c) an established, demestrable license application
. ture"is shown in Fig.1. At specific points in this step-by step review process.
4 177 MRS, LLW, AND TRANSPORTATION OF NUCLEAR WASTE Cosponsored by the isotopes and Radiation and the Fuel Cycle and Waste Management Divisions Session Organizer: J. C. Laul (PNL)
- 1. The Role of MRS and its impact on Facility aging at the repository. Consolidation would be perfoitned by Design, Christopher A. Kouts (DOE), invited extracting the spent fuel rods from the hardware that holds them together tn assemblies and rearranging them in a tighter The design of the U.S. Department of Energy's (DOE's) 8,rray for greater efficiency in storage, handling, transporta-monitored retrievable storage (MRS) facility has evolved ud tion, and disposal. -
will continue to evolve in the role that the facility will play After preparation, the canisters of spent fuel would be in the overau waste management system. The purpose of this loaded into shipping casks and shipped to the repository in paper is to review the evolution of the role of MRS in the dedicated trains. The facdity would also contain a large stor-waste management system and its impact on the design of the age yard in which the canisters of spent fuel wd3 be stored MRS facility. m sealed storage casks that would allow radiation monitoring Irtitially, after the passage of the Nuclear Waste Policy Act and easy retrieval for slupment to the repository, (NWPA) of 1982, the DOE intended the MRS facility to func. The MRS facility, in any case, would be designed and Onn as a backup storage facility for the first repository. The operated with the fundamental obj,ective of protecting the MRS facility,in this backup role, would be constructed only health and safety of the public, the workers at the fac0ity, and ifit was determined that the first repository was to be appre, the quality of the environment. It would be licensed to oper-ciably delayed. Initial planning for such an MRS fatTity in this ate by the U.S. Nuclear Regulatory Comaussica (NRC) and backup role indicated dat it could be constructed and oper. hence subject to both routine and unannounced inspections ating within a 4-yr period aftet a decision wss made to con, by NRC staff. It would be a shielded confinement-and-con. tainment facuity that would limit any releases of radioactive struct. During the development of the DOE's M5tS proposal to material to well below established regulatory limits, and its Congress, the role of the integrated MRS facility was studied safety-related features would be based on available and proven and developed. Its role was a significant departure from the technology. backup role previously endsioned by the DOE. The integrated Due to the passage of the NWPA Amendments of 1987, MRS facility, in addition to having a substantial spent fuel the DOE is m the process of reviewing the MRS design fea-storage capability, would also perform packaging functions tures to determme what changes might best improve the per-that were previously intended to be conducted at the reposi- formance of the overall waste management system, tory. Also, the integrated MRS facility would begin operations several years before the first repmitory commenced oper.ttions to help further a!!cviate spent fuel storage requirements at reactor sites. 2. The OCRWM Transportation Program- An Section 141 of the NWPA directed the Secretary of Energy Update, Lake Barrett (DOE), invited to perform a detailed study of the need for, and feasibility of, MRS and to submit to the Congress a proposal for the ese The Office of Civilian Radioactive Waste Management struction of one or more MRS facilities. On March 31,1987, (OCRWM) is developing the capability to ship spent nuclear in accordance with the requirements of Sec.141 of the fuel from commercial power plants and high-level radioactive NWPA, DOE submitted a proposal to the Congress to con. waste from national defense activities to a permanent geologic struct and operate one facility for the MRS of spent nuclear repository. This paper describes the progress to date in estab-fuel. lishing the transportation system. Related activities have cen-As further required by the NWPA, the DOE developed tered on three major areas: designs for two alternative storage conce, pts at three alterna- 1. resolution of institutional issues tive sites. The preferred storage concept ts surface storage m scaled concrete casks; the alternative concept is storage in field 2. cask system development dryweth. The three alterr tive sites wers au located in the state
- 3. support system development.
of Tennessee on land controued or owmed by the federal gov-ernment. 11 tis paper also addresses the implications of the recently The MRS facility, as envisioned in the proposal, would enacted Nuclear Waste Policy Act Amendments (NWPAA) on receive, prepare, and, as necessarv.
- tore spent fuel prior to program planning and activities.
emplacement in the first genlogic repository. The principal waste preparation functions would be spent fuel consolidation RE50!ETION Ol' INSTITUTION AL ISSUES and loading into canisters. Being uniform in size and free of surface contamination with radioactive material, these Interactions wie states, Indian tribes, utilities, and other canisters would faciFtate handling shipping, and further pack- parties having an interest in the transportation program have
6 178 MRS, LLW, and Transportation of Nuclear Waste led to the identification of a broad range of procedural, oper- and Indian tribes: training is to extend to procedures for safe ational, and Gnancialissues related to waste transportation, routine transport and emergency response situations. The issues identified to date include cask design and testing, pre. OCRWM is now in the process of reviewing the effect of all notification, routing, inspection and enforcement, and emer- such requirements on the technical and institutional elements gency response. To foster participation in the review of such of the transportation program. issues, the OCRWM has broadened the scope of its Transpor, tation Coordination Group (TCG) meetings to include sub-stantive discussion of both technical and institutionalissues. 3. Characteristics of Spent Fuel and High-Representatives from the states, Indian tribes, utilities, and Level Waste, Karl J. Nott (ORNL), invited transportation industry are encouraged to report on indepen-dent transportation activities and participate in the review INTRODUCTION of OCRWM program plans for transportation. In addition, The Office of Civilian Radioactive Waste Management workshops on specific issues have been scheduled to promote (OCRWM)is responsible for the spent fuels and high. level discussion of specific issues. wastes (HLWs) that will eventually be disposed of in a geo-The OCRWM bas also entered into contractua arrange, logic repository. The major sources of these materials are ments with national, regional, and transportation-related or. commercial light water reactor (LWR) spent fuel and immobi-ganizations to assist in the study of transportation issues and the cooperative development of policies and procedures. Co-lized HLW. The latter includes both commercial (West Val-ley) and defen>e.related sources (Savannah River, Hanford, operative agreements with the Southern States' Energy Board, and Idabo). Other sources include non-LWR spent fuel and the Western Interstate Energy Board, the National Congress miscellaneous sources. Detailed characterizations are required of American Indians, the National Conference of State Legis- for these materials. These characterizations melude physical, latures, and the Commercial Vehicle Safety Alliance have been chemical, and radiological properties; the last must take into initiated to support the study of numerous issues. secount decay as a function of time. In addition, the present and future quantities of the various wastes must be known or CASK DEVELOPMENT projected. This mformauon has been assembled in a charac. 1ne c.sk development program is divided into four initia- teristics data base, which proviJies data in four formats: hard-tives: the development of casks for shipping spent fuel from copy standard reports, user-oriented personal computer (PC) commercial reactors to a monitored retrievable storage (MRS) data bases, program-level PC data bases, and mainframe com-facility or to a repository, the development of carks for ship- puter fues. ping waste from an MRS facility to a repository, the deselop- This data base is an integral part of the systems integra- . ment of casks for nonstandnd fuel and nonfuel components, tion approach being used by OCRWM. As such,it provides and development of defense waste casks. The primary focus a stsndard set of data to the various areas of responsibility I of the program is currently en the development of "from- within OCRWM, including storage, trnsportation, and geo-reactor" casks. Initial plans of the OCRWM called for devel- logic dispasal The data are for use in design studies, trade-oping legal-weight truck casks, overweight truck casks, rail off studies, and system optimization. and/or barge casks, and storage / transportation casks. Because I of the uncertaintf of program requirernents, however, the DESCRIPTION AND RESULTS approach to this "from-reactor" cask initiative has been reeval- t' An objective of the report' is to consolidate into one doc-uated and revised by the OCRWM. Under the revised strat. umented data base pertinent waste characterization informa-egy,legalmeight truck casks and rail / barge casks will continue tion on all wastes that will or may be the responsibility of to be developed, but the development of overweight truck OCRWM. This includes the two major sources and two other I casks will be deferred, pending resolution of institutional sources cited above. These can be conveniently subdivided into f issues associated with overweight truck operations. In addj. eight waste categories, as shown in Fig.1, tion, the OCRWM's development of storage / transport casks There are five user-oriented data bases that provide will be deferred indefinitely. detailed information in a menu-driven system and require no computer programming capabilities by the user: TRANSPORTATION SUPPORT SYSTEM The development of the transportation support system (the 1. LWR radiological data base: contains radionuclide facilities and procedures needed to conduct operations) has comnasitions, heat generation rates, curies, and other infor-centered oa defining functional requirements for the system mation as a function of spent fuel type, burnup, and decay and a necos messment for various facilities, such as one for time. cask maintenance. An initial evaluation of system manage- .
- 2. LWR assemblies data base: contains physical and radio-ment options has also been completed. logical desenptions of fuel assemblies.
- 2. HLW data base: contains physical and radiological IMPLICATIONS OF RECENT LEGISLATION descriptions of HLW, both as the interim form and the immo-In December 1937, the Congress enacted the NWPAA. bilized form in canisters, Among its provisions, the aet authorizes the U.S. Department
- 4. LWR nonfuel assembly hardware data base: contains 1 of Energy to site and construct a repository in the state of Nevada, authorizes the construction of an MRS facility sub- physical and radiological descrip ions of nonfuel assembly ject to specific conditions, provides for a negotiator to seek a hardware.
state or Indian tribe willing to host a repository or MRS facil. $. LWR quantities data base: contains data on discharged sty, and addresses certain aspects of (ransportuion. The act fuel, as historical inventories and as projected quantities. requires the use of casks certified by the U.S. Nuclear Regu-In addition, two more PC data bases are under develep-latory Commission (NRC) and compliance with NRC preno-ment, one with data on LWR fuci pin characteristics and one tification regulations. (The OCRWM had predously indicated its intent to comply with such NRC standards.) The act fur- for LWR essembly serial numbers, ther requires provision of technical assistance and funding to The program-level PC files are more versatile than the user-onented files, but using these requires programming skills states for training public safety officials of local govern,nents
MRS, LLW, ana Transportation of Nuclear Waste 179 OTHER MISC. SOURCES HIGH-LEVEL W ASTE LWR SPENT FUEL SPENT W ASTES FUELS ir <r f y I BWR PWR WV SR RL 10 I ~p[EO SPOS L TREATMENT ! TREATMENT CAntSTERS ASSEMBLIES L __ _ _ _ ) _ (-- --- l CANISTERS l L _ _a
' I T f f CH A R AC TERIS TICS DATA BASE OATA BASE DATA BASE D AT A G Asti l l
WASTE STREAM l II " l l 9 AN ALY SIS g e 5 o o > : g
$ S $ $hO O U P
9 aa82r A 4 G
$omM > o D 0
> 0 m " $
h c C o o - 2 h m Mg y m M C m2o m C s c c p M o g Fig.1. Generic data sources for the characteristics data base. D ATA INPUT D ATA M ANIPUL ATION DATA OUTPUT FROM OTHER D A T A Fit.E S: M AINFR AME FILES
/ INPUT POP-10, IBM 3033 SIA
\ PROGRAMS 10 8 g "ST AND AR0 REPORTS PNL I FOR PUBLICATION NRC DOWNLOAD 4 AND REFORMAT S P E CI AL. R E P O R TS NMMSS IN RESPONSE TO J
EPRI i . USER REQUESTS MCC PC PROGRAM FILES ON HARD DISCS DOWNLO AD . AND REFORMAT NEW D ATA: / CREATE SELECTED DETAILS MANUAL PC USER-ORIENTED ON SCREEN OR
\ FORMAT INPUT FILES ON FLOPPIES HARD COPY FOR PERSONAL USE s
F Fig. 2. Data processing in the characteristics data base, with dBASE III. This permits tatulation of special reports and and radiological properties. These characteristics are calculated int:ractive output. The mainframe computer files are used to using ORIGEN2 and include the following: generate the above files and some of the hard<opy repcrts, g Their use requires extensive p,cgamming skill in SAS, FOR-TRAN, and other computer languages. The (Iow of data 2. radioactivity, total and by isotope (curies) through the data base is s,hown in Fig. 2. y ,; g ,g g, The chara?cristics of mterest mclude phys,i cal and chem-ical descriptions, existing inventories and projected quantities. 4. photon energy spectra, by energy group (18 groups)
MRS, LLW, and Transportation of Nuclear Waste 179 OTHER MISC. SOURCES HIGH-LEVEL WA3TE LWR SPENT FUEL SPENT WASTES FUELS it ir h- 0 WV SR PL 10 BWR PWR PREDISPOSAL TREATMENT # CANISTERS ASSEMBLIES L __ ) p--___ q
] CANISTERS l L .a 1f If if If' CMARACTERISTICS DATA BASE DATA BASE DATA BASE DATA BASE WASTE STREAM E 9 U ANALYSIS :g o 3 o o > z g y
$m $ $3O n e q O,-
U p
< b
- o h& h I
$' 6 m a g h
m a &C r p. m m> m . m 3 m 2 g e 5 3. m -o cm, , C r G > hk m b Fig.1. Generic data sources for the characteristics data base. DATA INPUT DATA MANIPULATION DATA OUTPUT FROM OTHER DATA FILES: MAINFRAME FILES
/ INPUT PDP-10, IBM 3033 EIA
\ PROGRAMS 10 8 g "ST AND ARD REPORTS PNL i FOR PUBLICATION NRC DOWNLOAD 4 AND REFORMAT SPECIAL REPORTS NMMSS IN RESPONSE TO EPRI I . USER PEQUESTS MCC PC PROGRAM FILES ON HARD DISCS DOWNLOAD .
-AND REFORMAT NEW DATA: / CREATE #f SELECTED DETAILS MANUAL PC USER-ORIENTED ON SCREEN OR
\ FORMAT FILES ON FLOPPIES 4
HARD COPY FOR INPUT PERSONAL USE Fig. 2. Data processing in the characteristics data base. with dBASE !!!. This permits tabulation of special reports and and radiological properties. These characteristics are calculated interactive output. The mainframe computer files are used to using ORIGEN2 and include the following: generate the above ales and some of the hard. copy reports. g ;, g Their use requires extensive progranuning skillin SAS, FOR. TRAN, and other computer lanFuages. The flow of data 2. radioactivity, total and by isotope (curies) through the data base is shown in Fig. 2. I al er, tM and h ism Ws) The characteristics of interest melude phys.ical and chem, ical descriptions, existing inventories and projected quantitles, 4, photon energy spectra, by energy group (18 groups)
1
~,'
180 -MRS, LLW, and Transportation of Nuclear Waste
$. neutcons from spontaneous fission (per second) site has identified the design issues that must be addressed either prior to initiation of the ACD or as part of ACD. The
- 6. neutrons from (a,n) reactions (per second) most important of these include emplacement configuration;
- 7. quantity of each element (grams or gram. atoms). retrieval strategyl design of the underground, including aUow.
able areal power density and usable underground area; waste These radiological characteristics have been tabulated for package strategy; preclosure safety and items important to LWR spent fuels as a function of fuel type and burnup and safety and waste isolauon: and seismic design considerations. fcr LWR hardware as a function of assembly type, materials The reference design for the Nevada repository has waste of construction, and location within the reactor core. A!! have canisters emplaced vertically in the underground. De option been decayed for 24 (or more) time periods, out to one mil- of horizontal emplacement in long boreholes extending out of g; " I'*"" the drift wall has been explored. llorizontal emplacement
9"I'.es less underground development and thus less material
- 1. "Characteristics of Spent Fuel. High-Level Waste, and handhng, less ventilauon, and lower cost. The feasibibty of
- Other Radioactive Wastes That May Require Long-Term this alternative, especially with respect to the ability to retrieve isolation," DOE /RW.0184, Vol.1 (Mar.1988), and Vol, requires further examination. The retrieval strategy for both 2 (May 1988), U1 Department of Energy. emplacement modes requires further development and dem-onstration of the technical feasibility. The reference repository design is currently based on an
- 4. , Waste Packs 9e and Under9round Facility allowable areal power density of $7 kW / acre. Alternatives as Design, Mark W. Fret (DOE), Nadia J. Dayem hjgh as 80 kW/ acre will be examined. The resolution of this (WESTON TST), invited design issue will require close coordination between the waste package and repository design efforts. The allowable areal ne design of the waste package and the underground power density will be a function of the waste package beat facilitv for radioactive waste disposal presents many chauenges load, the strategy for demonstrating compliance with the waste never before addressed in an enginectmg 4: sign effort. The package performance objectives, and the constraints on waste designs must allow for handling and emplacement of the waste package internal temperature, near. field temperature, and far-and must ensure that the waste will be isolated over time peri- field effects of heat load, ods that extend beyond those normauy dealt with in engineer- The usable underground area is an issue closely associated ing solutions. Once developed, these designs must be defended with the allowable areal power density. Resolution of this issue in a licensing arena to allow construction and operation of the will require determination of the stand-off distance required disposal systern, between waste emplacement areas and fracture and fault The design of the waste package and the repository is zones. This will define the lateral usable extent of the site and, being conducted iteratively. Each iteration of the design is when combined with the allowable areal power density, the accompanied by an assessment of the performance of the capacity of the site, design and an assessment of remaining design issues. These The reference waste package design is for consolidated assessments are used to establish the basis for the next design spent fuel packages having 18 boiling water reactor (BWR) phase. Design reouirem:nts are assessed and revised as neces- asse ablies or 6 pressurized water reactor (PWR) assemblies ury Ltfore the imtiadon of each design phase. In addition, the per package. The spent fuel that cannot be consolidated (as-de*igt effort is being closely integrated with the siting effort sumed to be 10% of the inventory) will be paged with through the application of an issue identification and resolu- 6 BWR or 3 PWR assemblies per package. Issues remaining tion strategy. in waste package design include the strategy for demonstrat.
De design phases are divided into two groups: conceptual ing compliance with the waste package perforretince objec-design and Title I and Title !! designs. Within the conceptual tives, materials fi. *he waste package, and the internal design design group are the conceptual design for the site character- of the waste package, including consideration of combining ization plan and the advanced conceptual design. The Title i PWR and BWR assemblies or fuelin one package or includ-and II design group includes the license application design and ing assemMy hardware in the consolidated fuel packages. the final procurement and construction design. These design The items important to safety and waste isolation will be phases adapt the phases normally employed in a U.S. Depart. designed to a greater level of detail throughout the design ment of Energy design to the licensing and procedural require- phases than other components of the design. A preliminary hst ments of the repository program, of these items wu developed during the SCP.CD effort. This The conceptual designs (CDs) for the site characterization list will be finalized, and detailed conceptual design will be plans (SCPs) focused on the design of portions of the repost- developed during ACD. tory and waste package that require site characterization data The design basis for incorporation of seismic design con-for their further development. This design phase supported the siderations will be finalized during ACD. The gravity forces identification of site information required as input to the de- to be used in design of the surface and underground will be sign and design information necessary to support assessment determined, and de-ign approaches for dealing with this of the site. ground motion will be established. During the advanced conceptual design (ACD) phase, design alternatives for all aspects of the repository and waste package will be explored and preferred design alternatives 5. State implementation of the Low-Level Ra-identified. Design licensing issues will be identified during dioactive Waste Policy Amendments Act: A ACD, and the approach to their resolution will be determined. Federal Perspective, Scott T. Hinschberger Design requirements for the beense applic.uon design will be firmly established as a result of the ACD phase. (DOE, Idaho), Terry D. Tait (EG&G Idaho), m. . The license application design phase will advance designs viled for the structures, systems, and components important to safety and isolation to the Title 11 level. De final procurement The January 1986 enactment of Public Law 99 240, the and construction design will complete the design of all aspects Low. Level Radioactive Waste Policy Amendments Act of of the repository and waste package to the Title 11 level. 1985, provided a series of milestones, incentives, and penal-The SCP-CDs for each of the three candidate sites were ties to encourage states and compact regions to fulfill their completed in 1987. Assessment of the SCP-CD for the Nevada responsibilities to safely dispose of the low-level radioacthe
4 - MRS, LLW, and Transportatiori of Nuclear Waste 181 wastes (LLWs) generated within their states. The act ensures _ west compact region does not intend to develop a new facility that LLW generators will have continued access to the three in the near future to replace its existing Richland, Washing-existing commercial LLW disposal sites through 1992 as long ton, site. as their states or compact regions are in cornpliance with inile. Based on the current regional configurations, the number stones prescribed in the amendments act for development of of potential "go-it.alone' states, and assuming that New new disposal facilities. . Hampshire, North Dakota, Rhode Island, District of Colum-Currently,41 states have joined nine compact regions to bia, and Puerto Rico will not develop new sites, the nation is provide for the disposal of LLW generated within their bor- currently facing the prospect of developing 15 new LLW dis-ders. Six states have declared their intentions to develop their posal facilities in addition to the existing Richland, Washing-own individual disposal sites. Two states have contracted with ton, site. At an estimated cost of $30 million (1986 dollars) to a sited compact region to dispose of their waste, and three develop a new site, the nation is looking at the possibility of states still have not declared their intentions for management a $450 million (1986 dollars) expenditure in new LLW disposal of their LLW. facilities over the next 7 yr. His potential increase in the num-The amendments act requires that, by January 1,1988, ber of sites, coupled with recent decreases in LLW volumes, each nonsited compact region shallidentify the state in which ' raises doubts about the economic viability of several of the its LLW disposal facility is to be located, develop a siting plan proposed new sites, for such facility, and elegate authority to implement such The objective of the Lo*-Level Radioactive Waste Policy plan. States that do not have operating disposal sites and that Amendments Act of 1985 is to ensure the development of an are not members of a compact must develop a siting plan for effective, safe, and environmentally acceptable nationwide sys-their facility and delegate the authority to implement such tem for the disposal of LLW by 1993. Several states and com-plan. pact regions have already expressed concern about their ability Host states have been named in all six of the unsited com. to meet the milestones mandated by the amendments act. Only pact regions as shown in Table 1. Although not rcquired by 8 of the 15 proposed new sites are schedu'ed for operation by
- the amendments act, both the southeast and the Rocky Moun- January 1,1993. Not counting the two replacement facilities I tain compact regions intend to close their existmg facilities at in the Rocky Mountain and southeast compact regions, only the end of 1992. Successor host states have been selected for 6 of the 13 new disposal facilities being developed under the both regions. Colorado has been nained to replace Nevada in requirements of the amendments act may be operational by the Rocky Mountam region, and North Carolina will supplant the begmrung of 1993. Therefore, beginning in 1993, the LLW South Carolina in the southeast compact region. The north- generators in 21 states may not have access to available dis-posal facilities, and the affected states must provide for the management of the LLW generated within thU states until the new state or regional disposal facility is available.
TABLg i Siting disposal facilities for LLW is a complex prob! m, State, Reg.onal Summary composed of many technical, economic, political, institutional, and environmentalissues. As a result, the development of new compact Fasty disposal faciliities is taking longer than expected. No new Region Host State Operational waste disposal facility has been sited 14:the United States since Apulachtaa Peans y1Hala J iy 1994 .971, and no license application for any disposal site (includ-mg the three existing sites) has ever been filed in accordance central tetrasu Jaavary 1993* with the requirements of 10CFR61, "Licensing Requirements Janney 1993* f r Land Disposal of Radioactive Waste " which,was prornul-centrol rie est 111tnets gated in 1983. Sorne of the major issues afi'ectmg state and ste.est utentesa tu t e.oe r 1993 regional progress today include the schedule imposed by the amendments act, site development costs, mandate for alterna-nortnent me. Jersey aa4 sote.uc 1994 tive disposal technologies, stability of compact regions, avail-
- coauctscut July 1994 ability of liability insurance, public and political opposition to siting LLW disposal faciliucs, and the limited availability of hartan st wasnington (entsting) II/A state and compact region resources.
aan y mur.tain* knaq (anisttag) t/A ' Ole formHion of cornpact regions appropriate to waste disposal needs rem: ins a dynamic process. The need for exten-
<:elersee Jaan ry 1993*
sisc public invohement in the development of the disposal site So tnust seeth Carellu (Histtag) N/A has placed further demands on the facility development pro-cess. Political, institutional, legat and economic factors are nortn ca entu Jaa ary 1993* still materially affecting the development and stability of the western Art uu Jaanry 19s3* regional approach to managing LLW, tuneu.at caisterais Joi,1,9c t w o.aveat mu Joty tess
- 6. The NRC Reviews of Low-Level Waste tuneaan puianoutta su t.n er tesi Forms and Corstainers, Michael Tokar (NRQ,
- =e. ,en Jaan cy i m '
, t nue.uee t invited 3 ru.nanat r.us Joury im* - , As stated in the U.S. Nuclear Regulatory Commission tu n ean at ver at (NRC) regulation (10CFR61) for land dispoul of low level Note: Nortn Oakote. Now Hamoe.re. and Puerto Raco are undeclared, radioactive waste (LLW), class B and C wastes must have structural stability. Part 61 also indicates that a structurally
*Then comoscts or stres w,u mut or uceed the January 1993 deadhne in the saw. stable waste form is one that will maintain its physical dimen-
*oinmt of columo a and Rhode is and have contracted with the sions and form under expected disposal conditions, including v Mountain compact to d soose of toen iowdevei weste enrougn the weight of overburden and coripaction equipment, the
- vermont has not ,ssued a seemg ph presence of moisture and microbial acuvity, and internal fac-
~
182 MRS, LLW, and Transportation of Nuclear Waste nors, such as radiation effects and chemical changes. Howeser, solidification agents or HICs in response to the current TP. beyond describing some general charactenstics to which the A total of 25 reporu have been submitted. Of these,4 (2 HICs waste must conform, such as limits on the amount of free. and 2 solidification agents) have been approved,5 have been stand 2ng liquid and the avoidance of pyrophoric material, the withdrawn, knd several more are nearing approval. regulatioc provides no gu dance on how LLW can be demon-strated to have the required structural stability. That type of guidance is provided in a Technical Position (TP) on Waste 7. ' The EPA Low. Level Waste Standard- A Form Stability, which was issued in May 1983. Thus, to meet Status Report, Floyd:L. Galpin, James M' the requirements of 10CFR61, vendors of high integrity con- Gruh/ke, William F. Holcomb (EPA), mvited tainers (HICs) and waste solidification agents develop test data for their HlC designs and waste formulations in accordance . The Environmental Protection Agency (EPA) is devel. with recommendations provided in the 1983 TP. De data are ping generally applicable environments' standards for land then submitted with a topical report for technical review. The disposal of Atomic Energy Act (AEA) low-level radioactive technical review is intended to lead to a conclusion that the wastes (LLW) and certain naturaDy occurring and accelerator. HlC design or solidification agent fonnulation meets the sta- pr duced radioactive material (NARM) wastes. bihty requirements of Part 61 and thus is acceptable for dis. It is EPA s intention that the LLW standards will protect posal at a LLW disposal facility. public health and the environment. The LLW standards would The guidance provided in the 1983 TP is in the form o'f CMer sposal of aU AEA materials, not controDed by other recommended tests that address the effects of the expected dis- EPA standards and some natural radioactive ma'erials. Cover. posal conditions. For solidified waste forms, the tests essen. age federal waste is sigruheant, because the federal govern-tiaDy involve subjecting the waste for specimens to conditions ment generates and disposes of >40% of au LLW nationwide, of compression, irradiation, biodegradation, leaching,immer- a d a umform s,tandard for au LLW disposal is both a destr-sion, and thermal cycling. The tests are based on American able and an actuevable goal. Publication of a proposed LLW Society for Testing and Materials or American Nuclear Society standard is planned in 1988, and a final standard a year later. standard test methods that were in most cases oririnally devel- This standard will have several important and closely oped for specific nonradioactive material applications. Dese te a areas f cus: test rnethods are used to demonstrate, by means of exposing test specirnens to relatively short-term (minutes to weeks) pro- 1. LLW predisposal operations, storage, and manage. cedures, that LLW would have the desired long-term (300-yr) ment: This would hmit annualindividual exposures from all structural stability, environmental pathways to members of the pubbe from au Shortly after release of the TP, the staff began work on away from-generator processing facilities, all LLW disposal turning the TP into an official Regulatory Guide (RO); fTPs sites, and au DOE f acilities that process, manage, or store commonly serve as precursors for RGs, which are another LLW. type of NRC guidance document and which are similar to TPs The EPA deems it prudent to include limits on these except that the RGs are required to undergo a formal peer potendal exposures in our standards. This would also make review and comment process that also involves pubhc partic. the EPA LLW standards parallel and consistent in structure ipation). Several working drafts of an RG have been gener. with the standards EPA promulgated for the uranium fuel ated; one of these drafts has received limited circulation, and cycle,40CFRl90, and high-level radioactive waste,4CCFR191. comments have been received from certain sectors of the nu. 2. Definition of radiation exposures related to radioactive clear industry such as the Nuclear Management and Resources Council (NUMARC). Tbc NUMARC study recommended waste disposal that are sufficiently smau that they either do that certain acceptance criteria caUed for in the TP tests and not need to be tegulated regarding their radiation hazard or the wastes can be disposed of with minimal controls,i.e., a draft RG should be modified. Those conclusions and reecm. mendations appear to be the resuh of an assumption that the level"below regulatory concern"(BRC): The EPA would not test conditions should duplicate the conditions expected in the be involved in identifying or selecting specifie LLW tmes that disposal facihty. That assurnption is inconsistent, however, qualify as BRC wastes: the U.S. Nudear Regulatory Commis. with the NRC staff's objectives for the recommended tests and sion, states, and U.S. Depanment of Energy would implement acceptance criteria provided in the TP and draft RG. the use of these criteria. Those wastes identified as BRC wastes, and not having hazardous characteristics as dermed in Taking into consideration the comments from the various the Resource Conservation and Recovery Act, would be dis. industry and NRC oversight groups that have taken an interest in waste form stabihty testing, the NRC staff has cortinued posed of as trash in a municipal sanitary disposal facility or be incinerated and subsequently so disposed. The risk analyses to address changes that might be appropriate in the recom. show that with careful selection and segregation of waste, the mended test procedures or criteria. The basic questions being addressed by the staff are, *What parameters should be tnea. population, individual, and on-site nsks can be gtute low. For a 0.01 to 0.04 mSv (1 to 4 mrem)Sr criterion, the maumum sured, and what kind of sbon term tests can be used to dem. onstrate that a waste form will retain its "form" over a 300 yr estimated lifetime risk for the criticalindividual would be of the order of 10", whue reduems the volume of regulat2d period?" Retention of form is intended here to mean that the w aste form will not disintegrate into its component materials, waste by up to 35%, and a 20 yr savings of up to 15 80 milbort it is notable that at present the pnncipal parameter of merit for soboified waste forms is compressive strength; this is the 3. Radiation exposure limits to individuals after the dis. posal site is closed, i e., after it stops receiving waste: The acceptance parag.4ter for all the TP waste form tests other standards will establish limits on exposure through all path-than the leaching test. Whether a given minimum compressive ways to members of the pubbe and apply to any LLW du. strength s alue can, in and of itself, provide assurance of long. term structural stabihty,is of particular concern and may take posal facility using any land disposal method anywhere in the a lengthy period of time to resolve. For that reason, a target United States. date for release of a revised RG cannot be provided at tha
- 4. Groundwater protection for both pre- and postdapod time.
While searching for potentially more appropriate waste phues: The protection of the nation's groundwaters is cf form tests and criteria, the NRC staff is continuing to review major importance in EPA. The EPA's groundwater protectiori the topical reports that have been submitted by sendors of strategy calls for the protection of groundwater commensurait 1
MRS, LLW, and Transport;: tion of Nuclear Waste 183 with its value and use. Class I groundwaters require the high- veys, surface water flow analyses, seismic work, well-drilling est levels of protection and represent those that serve as irre- and boring log evaluation, and ethnographic studies. Local ad-placeable sources of drinking water for large populations, visory comnuttees (LACs) were formed for each candidate site Therefore nondegradation criteria are being considered. For to help in charactertzing the socioeconomic and environmental class 11 potable groundwaters, EPA is considering two pro- setting for the sites and to identify local project concerns. posed options. The first would require using 0.04 mSe (4 Local nominations w ere sought to form the local committees, mrem)/yr as the limit. In the second option. Class !! would The League of Women Voters convened the LAC meetings, be divided into subsets. The high yield class !! groundwaters provided support to members, and established project docu-would use the 0.04 mSv (4 mrem)/yr standard, and the re- ment repositories in the siting area through county library sys-maining low. yield class !! groundwaters would be subject to tems. US Ecology also established local information offices to a standard of up to 0.25 mSv (25 mretn)/yr. provide convenient access by local citizens to project techni-cal rep rts and sponsored tours of the Beatty, Nevada, dis-
- 5. Other areas will include guidance on implementation posal fac@y to wh an pistbg operada, and qualitative assurance requirements. These requirements US Ecology systematically integrated citizen involvement address areas not appropriate for quantitative requirements. into the techmcal studies leading to candidate site selecuon.
They inciude active mstitutional controls, such as guarding s approach fuhd two unponant oWses. Est. com-and maintenance; passive institutional measures, such as per- munity leaders and members of the public received accurate manent markers; monitoring during disposal and postdisposal
.nformation on the nature of low level radioactive waste and phases; and location away from areas containing materials not the ennronmental conditions appropriate for its disposal. The wideif available from other sources. extensive schedule of public outreach activities spread over
- 6. High concentration, relatively low volume NARM time reinforced this educational objective and fccused public wastes in the same standard promulgation: The Toxic Sub- attention on where (rather than if) the site would be built. Sec-stances Control Act is being considered for the necessary ond, the public was actively involved in deciding the way dis-authority to ret,ulats VARM wastes. To define which NARM cretionary siting criteria were used to narrow down technically wastes should be subject to the LLW standard, a specific suitable areas to specific candidate sites. The result, identifi-activity of 37 to 74 Bq (1 to 2 nCiVg is being considered as cation of two technicauy sound sites receiving strong local sup-a lower limit for applicability of the standard's requirement. port, recommends this approach for future siting efforts.
Regulation of these specific NARM wastes will(a) assure the same protection from disposal of discrete nondiffuse, low-volume, high. activity NARM wastes as for similar AEA wastes; and (b) provide for a manifest system that will track the 9. Organic Diagenesis in Cornrnercial Nuclear NARM waste from generator to disposal. Wastes, Anfhony P. Toste, Teresa1. Lechner-Fish (PNL)
- 8. Siting a Low Level Waste Facility in Califor- IN1RouccTioN nia: A Success Story, S. A. Romano, R. K. Gay- .
'**'* ""* * * *h**'"**
" * ' "d * '""d' nor (US Ecology, NesIort Beach), invited I.arge volumes of already existmg wastes must be permanently disposed using environmentally acceptable technologies. Nu-US Ecology is the state of California's designee to site **** #'i'.eria must be addressed before wastes can be per-develop, and operate a low-level radioactive waste disposal "'" ' "'*#* # " # I*
* * "
- Y d**P '
facility. The facility will meet the state's responsibilities under ' " P ' the Low-Level Radioactive Waste Policy Act as amended. By m* s mplex ne\ g o in rganicsMio-January 1988, US Ecology narrowed its efforts to two candi- chemicals, and, occasionally, organics. It is clen, for example, date sites. Strong local community support has been expressed that organics have been used extensively in nuclear operations, for both sites. US Ecology mil select a mogle proposed site for such as waste reprocessing, and continue to be used widely as licensing in 1933 and anticipates receiving waste in late 1990 solvents, decontamination agents, etc. or early 1991. This schedule places California well ahead of Our group has analyzed the organic content of many kinds the muestones identified in federal law. The success to date m of nuclear wastes ranging from commercial to defense wastes. California can be attributed in large part to the open process In this paper, we describe the final analyses of three commer-used to tovolve citizens' advisory committees (CACs) and the cial wastes: one waste from a pressurized water reactor (PWR) general pubhc at critical stages of the project
- and two wastes from a boiling water reactor (BWR). The
, US Ecology was selected to establish the disposal facility PWR waste is a boric acid concentrate waste. The two BWR m December 1985. In early 1986, the company identified 18 wastes, BWR wastes Nos. I and 2, are evaporator concen-desert basins in southeastern California for siting considera- trates of liquid wastes produced during the regeneration of tion. A CAC was then formed to assist US Ecology in defin- ,
ion exchange resins used to purify reactor process water. In mg and applung disposal site, selection criteria and m involving preliminarv analyses, which were reported previously, we desert residents in siting decisions. A grant was provided to the detected a few known organics and myriad unknowns. Recent League of % omen Voters to support the committee's work. reexamination of mass. spectral data, coupled with reanaivsis Information on the siting areas was gathered and entered of the wastes, has resulted in the firm identification of the mto a computerized datt. base to screen out unsuitable areas unknc ens. Most of the compounds, over thirty distinct or-and to focus on those locations l'aving the greatest opportu- ganics, are derived from the degradation, or diagenesis, of tuty for development. This mapping effort displayed informa- source-term organics, revealing, for the first time, tha organic tion on Isad use and ownership, transportation, wilderness diagenesis in commercial wastes is both vigorous and varied. and recreation areas, wildlife habitat, cultural resources, flood plains, fault tones, and estimated depth to groundwater and bedrock. After three rounds of public meetings and workshops ANALYTICAL APPROACil and six CAC meetings, US Ecology named three candidate sites in Tebruary 1987. ~ ~ ' Analyaing oreanies in nuclear wastes poses numerous Site characteriution studies were thee :nitiated at the three challenges. The wastes typically exist as high-ionic-strength, sites. They included biological and archaeological field sur- mixed phase samples that may be highly radioactive, making P h
i W
.184 MRS, LLW, and Transportation of Nuclear Waste them very difficult to bandle. Fortunately, specialized radia. BWR wastes, but the PWR waste also contained some. Such tion facilities and analytical advances made in recent years, compounds are typically used as hydraulic fluids and plasti-e.g., the development of high-resolution capillary gas chroma- cizers in industry, tography (OC) and computerized GC/ mass spectrometry (GC/MS), f acilitate the tuk. Hydrophilie Organics The three commerdal wastes, consisted of mixed liquid and Several classes of hydrophibe organics were identified in solid phases, necessitating special sample preparation proce- the wastes (Table II). Tbc most notable classes are the chelat.
dures. Each liauid phase was concentrated to dryness and ing/ complexing agents and a relued class of organics, the che-chemicaUy derivatized, followed by solvent extraction, yield- lator/complexor fragments. These organies best typify the ' ing hydrophobic and hydrophilic organic extracts. Each solid PWR waste. Of these organics, only ethylenediaminetetra-phase was extracted with water,and organic solvents: the acetic acid (EDTA), nitrilotriacetic acid (NTA), and citric, extracts were then prepared as bqu d phases. Finally, each oxalic, and glycolic acids are used commercially, e.g., as che- . organic extract was analyzed by GC, GC/MS, and GC/Fou- I lating or complexing agents in decontamination campaigns. rier transform mfrared (GD/ FTIR) spectroscopy for its or. .. ganic content.
- Organic Diagenesis
-- >=
~
I' RESULTS AND DISCUSSION , Most organies identified in the wastes'are undoubtedly derived from the diagenesis, or degradation, of source. term ; Hydrophobie Organics organics used m nuclear operations. For example, the chela. + Numerous hydrophobic organics were identified in the tor /complexor fragments derive from the ebelating/ complex-commercial wastes, particularly the BWR wastes, at relatively ing agents, and the carboxylic acids presumably derise from high parts per million (ppm) concentiations (Table I). The alkanes, or normal paraffin hydrocarbons. three most abundant classes of compounds were a family of The abundance of organic diagenesis products in the alkylphenols, two families of alkylphenyl phosphate esters, wastes, particularly the PWR waste, indicates that their chem. l and several phthalate esters. These compounds best typify the istries, particularly their organic content, are not static but t TABLEI Hydrophobic Organics identified in Commercial Nuclear Wastes' Concentration (ppm)* BWR Wastes PWR Wast: No. I No.2 Liquid Solid Liquid Solid Liquid Solid I Alkyl Phenols Creso1(Methylphenol) 1.5 3.2 25.g 43 5.9 11.1 13 14.4 0.7 16.2 Dunethylphenols (3)* 7.1 3.9 8.8 1.7 9.5 $ Ethylphenol ' Cyphenols (6)* 10.8
- 89.7 163 17.2 /
03 13 0.5 2.6(da-t-butyl)4-ethylphenol , 6.4 4-methyl.2-nitrophenol ' 1.6 Ethylrutrophenols Q)* 1 ,. 1 Phosphate Esters Di(a'kylphenyl)methylphosphates (3)' 73.2 i 15.4 11.1 2.9 , Tri(a'kylpheny!) phosphates (22)* Phthalate Esters Dioetylphthalate 33.2 btmethylphthalates (2)* 14.4 13 0.1 1.8 0.2 1.2 Aikyl@thalate HydroxytmaMehyde 4 (y - N-(pbenylmethyllanune 0.8 0.9 0.8 biene Sulfor.smide 03 Polyethylene Glycol {3
' Wastes obiained from a PWR and a BWR.
'No entry indicates compound is below detection level (0.1 ppb). j
' Number of compounds identified. '{ Lj 3
}i -
d
' MRS, LLW, and Transportation of Nuclear Waste 185 dynamic, or everchanging. Many wastes contain high radia. sibly, biological energies act on the source term organics to tion fields, exist at elevated temperatures, and have harsh iror- degrade them, even relatively stable compounds like cheladng genic matrices, e.d., high ionic strengths and extreme pH's. egents. Our research suggests that tb chemical transforma.
The associated chemical, thermal, radiolytic, and, even pos- tions can be diverse and very vigorous.
. TABLE 11 Hydrophilic Organics identified in Commercial Nuclear Wastes * ,
t Concentration (ppmn' ]!. BWR Wastes' I PWR Waste No.1 No.2 Liquid Liquid Solid Liquid Solid t Chelating / Completing Agents Citric Acid 7! 1.2 OA Nitnlocnacenc Acid (hTA) trace Ethylensilammetetram: etic Add (EDTA) 11.2 2.1 66.8
- Chelstor/Complesor Fragments '
N4di-metyl)immoacetic Acid 03 N4 ethyl)emylmmEstQw N acade Acu irme N4di4thyl)ss.etemy Acid 0.9 d Me&ylenediamme N<arb):/-N'-acede Acid 2.0 Methylenaliamine N.N<=tnayaceae Acid' 23 N4di-ethyl)irrunoacetic Achi IA Inunodiaceoc' Acid 03 N(2-hydroxyethyl. ethyl)inunoacedc Acid 1.0 N42-hydroxyerhyl)iminocartmaypropioruc Acid' O.4 i Methylinunodiacedc Acid 02 d N4etyl%$ylene&anune N-amdc# carbary Acid 64 N4 ethyl)e:hylenedismine##<arhasya: enc Acid
- 3A N4methylimmocartmay)ethyler. arm +N aceae Acd* rax N-(methylaminskninodiacede Acid 43 N.[2 hydroxyethyl #-cartety 2-(methylidine)]ethyliminocedc Acid' l.5 d 12A 1.8 Ethylenatianunetriaceoc Acid N-(rnethylamineW4rnethyl) ethylenediamine #N diacede Acid 13.2 N42 carteryethyl)immcdiacenc Acid 3A i N4methylamine)-N'-(ethyl)popylenediamine.NN diacetic Acid race Dicarboxylle Aelds 0A3 66 7 207 2 31.0 1A (e g.Osalic Acid)
Monocarbos)lle Aelds 3.1 131.5 45 (e s.Hemmiecanoic AeM) Oxygenated Aelds 16.2 141A 18.6 6.9 (e g.Glymlic Acid) Aromatic Aelds (e g. Benzoic Acid) 17.4 4.2 34 Ketones
- 1A 1A 3.6 (eg.4 MedorybmraMehyde)
- Hydrophilic orgarucs: rnethylated3(BF / methanol, acids idendfied as methyl esters); wastes scre obtained from a PWR and a BWR.
*No entry indicates cornpound is be!ow detecuon level (0.I ppb).
'PWR waste eusted as se state liquid and solid (30re ) phases at room temperature:(BWR No. I: 63*e liquid,37*e solidh (BWR I
No. 2: 47reliquid. $3re solidl.
*$olid phase of PWR waste contained no identifiable organics.
*1dentified by GC/MS and GC/ FTIR as a lactam. ,
' identified by GC/MS and GC/ FTIR as a lactone, I
r
i 186 CHARACTERIZATION OF HIGH-LEVEL WASTE SITES Cosponsored by the isot0phs and Radiation and the Fuel Cycle and Waste Management Divisions Session Organizer: Alec Van Luik (PNL) All Papers invited
- 1. Overview of the DOE Site Characterization A summary of the overview of the Nevada site character-intion consultation draft si well as a summary of current Program, Stephen H. Kale (DOE) activities to apply the requirements of the 1987 Act to the repository program is included, together with a brief status Last year was a period of significant progress and great report on regulatory issues and our cooperation with foreign change in the U.S. Department of Er.e gy's (DOE's) civihan radioactive waste management program. Progress ar'd change repository programs, were particularly evident in the DOE's site characterization activities.
The construction of an experimental shaft for evaluation 2. Site Characterization and its Role in Reposi-of a potential repository site must be preceded by the publi- tory Licensing, Ralph Stein (DOE) canon and public review of a site characterization plan (SCP), and much of 1937 was spent in the preparation of such plans The Nucler Waste Policy Act of 1982 and the recently for the three sites under consideration in the states of Nevada, enacted Nuclear Waste Pohey Amendments Act of 19S7 (the Texas, and Washington. The plans are lengthy and technically Acts) specify a schedule and a process for the siting of a complex. In consultation with the states and Indian tribes that repository at Yucca Mountain. Nevada. A key step is the col. would be af fected by the plans, we determined that the opti- lection of geotechnicalinformation as described in a site char. nium procedure for resiew and adequate consideration should acterization plan (SCP). The information to be secured should involve the publication of consultation draft SCP: accompa- fully support th6 techrdcal data needs for a license application nied by oveniew documents early in 1988, to be followed by to the U.S. Nuclear Regulatory Commission (NRC) for technical workshops during the first quarter of the year. We authorization to construct a repository. Although the Acts also r,etermined that plans for morJtoring and mitigation of only require a general plan for site characterization, the U.S. the environmental and socioeconomic impacts of characteriza. Department of Energy (DOE) has, as a matter of policy, pie. tion (hiMPs), along with our plans for comphance -th all pared a comp,ehensive and detailed draft SCP that includes applicable regulatory requirement;(ERCPs), should be made available geotechnicalinformation about the site, a descrip-available with the SCPs. The SCP consultation process is typi. tion of the conceptual design of the repository, a descripuon cal of efforts throughout the year to mate the DOE's inter- of the waste package, and a detailed discussion of the plans actions with the public 'nore effective. for characterimns the site. One absolute requirement of the site characterization pro- The program described in the SCP places primary empha-cess is a quality assurance program adequate for licensieg a sis on the techrdcal sufficiency and adequacy of the proposed repository facility by me U.S. Nuclear Regulatory Commis- investigations to ensure that all the potentieDy needed technical sion. Great progress has recently been made in that area. Fol. information for siting, design, and supponing licensing will be lawing the issuance of stop-work orders involving the obtained. To accomplish this, an issues hierarchy has been repository program in 1906 to improve procedures and record- developed that provides an organinng framework for trans-keeping, a series of readmess resiews have been completed that lating applicable regulatory criteria into a testeg program. The resulted in the lifting of all orders in December 1937. We feel SCP is directed primarily toward identifymg performance that we now have a viable quahty assurance program for all measures relevant to identified issues, determining appropri-aspects of site characterization, but are continuing to exam- ate parameters for the performance measures, and developmg ine the pogram closely in an effort to strengthen it further, a testing strategy that will secure the information needed for The biggest change in the site characterization program ultimate resolution of the issues. has been the result of the passage on recember 22.1987 of the Demonstrating compliance with arpropriate regulatiom Nuclear War:e Polisy Amendments Act of 167 (tbe Act). The requires an initial licensing strategy based on a vision of chmination of the Texas and Washington State sites from the prospective informational needs. These needs are subject to site charactenzation process will result in a concentration of revision as experience and new mformation from testing and efforts on the Nevada site. The consultation draft SCPs as analyses become available. As a result, site characterizatior weD as the htMPs and ERCPs for Texas and Washington will should be viewed as an evolutionary and flerathe process. An3 not be issued, but those for Nnada were released on sched- changes identified as necessary will be documented in the seme ule on January 8,1981. Wotkshops are now designed for annua: progress reports that will be made available for review muimum consuhation value to Nevada. by all interested parties. This iterative process will eventualh I i I
l Characterization of High Level Waste Sites 187 c2J to the finallicensing strategy for obtaining authorization suitability. In the event that the information acquired supports f or construqion of a repository. a determination that the Yucca Mountain site is suitaM:,it will Within the abose cenceptual framework, the Yucca Moun- be recommded for development as a repository, if the taan site charactenzation will emphasize the follow'ng areas for Yucca Mountain site is determined not to be :Jitable, it is attormation deielopment: expected that Congress would direct the DOE to reinitiate tre
"" " P P " "
- 1. unsaturated zone, now characteristics to determine if the [#[,"dn R9 percolation flux is low and that the water m the unsatu. The actions required in the Amendments supplant many rated zone is tightly confined within the rock matrix of the procedural steps prescribed in the NWPA and incorpo-
- 2. site characteristics (e.g., geochemistry) affecting perfor. rated into the siting guidelines, They remove the requirement mance of the container, the waste form, and transport to consider alternatise sites for the first repository, and, fur-of the radionuclides in the unsaturated zone, and the ther, repeal the previous requirement to consider sites for a geohydrologic characteristics of the satuated rocks that second repository. The DOE is directed to report to the Pres-underlie the unsaturated zone ident and Congress in ~20 yr as to the need for a second repository. Site-specific activides with respect to a second site
- 3. unlikely processes or events that might disturb site chat-are prohibited unless specifically authorized and appropriated actensues by Congress.
- 4. preclosure radiation safety and the effects of seismic. With the focus of attention thus being brought to the ity on the surface and undarground facilities. Yucca Mountain site, the role of the implementation guide-lines is diminished. However, the technical considerations of The site-specific data gathered from site characterization the post and preclosure guidelines are still appropriate to the mil be cot.tinually tested against the issues hierarchy and the determinadon of site seability and are now to be emphasized appbcable regulations to judge the adequacy of the data. As as site characterization focuses on the Yucca Mountain site, sufficient data are collected and analy7ed, interactions will be The techrdcal considerations of these guidelines were incorpo-iniuated with the NRC to determine whether sufficient under- rated into the issues hierarchy and issue resolution strategies standing of the issue has been achieved to consider the mat- that provide the organizing framework for the site character-ter closed. This complex undertaking is unprecedented in ization program presented in the site characterization plan.
terms of the intensity of study of a particular location and its During site characterization at Yucca Mountain, information environs, the scrutiny that the conduct and results of site char- will be acquired to demonstrate whether allissues have been aciertzadon will receive, and the cost-estimated to be approx. resobed and whether comphance with the siting guidelines has ircatel> 51B for the program. For these reasons, DOE mtends been achieved. Evaluadon and analysts ro this informadon wiu to e .me ths' e:ch of the tests, analyses, and activides in the be even more rigorous than previously envisioned, as, with the s** characterizadon program is necessary to support licensing Congressional selection of Yucca Mountain as the single site of the repository and is included in the plan; that unnecessary for characterization, the program has now been brought more or redundant tests, analyses, anti activnies are not conducted; closely to tha hcensing phase of imeraction with the NRC. The and that the program is based on sound management and fis- informadon will create the basis for deseloping the license cal prudence. appUcation if, at the completion of site characterizadon. Yucca Mountam is determtr.ed to be suitable, and for support-ing the proceedings to receive a coristruedon authortzadon. As
- 3. Implementation of 10CFR960- A Regula- characterization proceeds, data, analyses and results will be tory Perspective, Carol L, Hanlon (DOE) presented in technical, topical, and issue resolution reports.
These reports will be used to formf.y close issues with the The Nuclear Waste Policy Act (NWPA) of 1982 required NRC as characterization proceeds and conclusive results are the U.S. Departrnent of Energy (DOE) to develop general obtained, and to provide references to the license applicadon. gudelines to be used for recommending sites for repositories. Fouowing exte=irc cesultation with states and tribes, inter-action with reouisite federal agencies, and concurrence from 4. U.S. Strategy for Evaluating the Yucca the U.S. Nuclear Regulatory Commission (NRC), the DOE Mountain, Nevada Site, Carl Gem (DOE, La5 promulgated its final siting guidelines,10CFR960, in Decem- Vega5) ber 1984. Because of the PW of the Nuclear Waste Amendments of December 1987,(the Amendments) the DOE The principal role of a disposal system at Yucca Moun-has reevaluated the sontinued role of the siting guidelines in tain, Nevada is to isolate waste for a long period into the the sharacterization of the Yucca Mountain site in Nevada, future. Therefore, the general objectise for the entire system The sidng guidelines were intended for use by the DOE for is to limit any radionuclide releases to the accessible environ-systematically esaluating potential sites for both a tirst and a ment This objective will be achieved by selecting a site that second repository. They were to be applied rigorously in eval. contains natural Lirriers against radionuclide releases and by ustmg a progressnely smaller number of sates according to the providing an appropriate system of engineered barriers. To specific requirements of the NWPA until a single site was rec- provide additionalinsurance that the system at Yucca Moun-ornmended for deselopment as a repository. The 10CFR960 tain will perform adequately, individual objectises have also contains two major sets of guidehnes: postelosure guidehnes, been defined for the engineered and storal barriers to radio-wrtich specify factors to be evaluated regarding the potential nuc!ide release and for the design of the disposal system. The [
- site's performance after closure; and preclosure guidelines, general objectne for the engmeered b rriers is that they should which sgcify factors regardine the eg med repository perfor- hmit the release of radionuclides to the natural barriers. The l
i mance danng concucten, operation, closure, and decomfrus- general objective for the natural barriers is that the time of siomos. In add tion,10CFR960 contains implerr.entation radionudide travel to the accessible environment through these l guidehnes, which state bow the post and preclasure guidehnes barriers should be very long, in pamcular, since groundwater are to be apphed and incorporate the consideration of diver- may transport radionuchdes, the grourdwate travel tirne s:tv into the identification and evaluation of utes, should be very long. The general objecthes for the design of The Amendments modify the DOE's mandate by specifi- the disposal system are that its operatinn should be safe and callY selectmg the Yucca Wuntain s!!e in Nesada for conduct tht! Its Construction should not cutpromise its abihty to meet of the site charatterization actntties required to esaluate its the other general objectnes. l I
s. 188 Characterization of High Leve! Waste Sites , Prioritics for the testing program can be inferred from the sinking techniques related te an exploratory shaft facility, and choices made for the top-level strategy; that is, the elements predictive code and model developrnent, identified and the espected role of these elements with regard
- 2. Test plans and designs are being developed by experi. t to the general objectives suggest the priorities for the investi. ment committees consisting of U.S., Canadian, and other ii gations in the site c'.aracterization program. The top level leading experts in their field. Test plans have been developed strategy to address these objecti ves at the Yucca Mountain site for excasauon response experiments, heated block experi.
leads to the following areas of ernphasist, -- ments. heated pressure chamber experiment, single fracture
- 1. unsaturated. zone flow characteristics - migration experiment, buffer / container experiments, borehole sealing investigations, shaft seahng investigations, instrumen.
- 2. site characteristics (e.g., geochemistry) affecting perfor.
mance of the container, the waste form, and transport tad,on developmera, shaft design, characterization and stabili. of the radionuclides in the unsaturated zone, and the zau n of fracture zones, shaft borehole probe, and shaft extensi n characterization techniques, geohydrologic characteristics of the saturated rocks that underlie the unsaturated zone 3. In adcition to test plans, several ha situ experiments have been performed, including excavation response and frac.
- 3. unlikely processes or events that disturb site character. ture resp nse measurement at the 240-m level and in the shaft istics using instrumentation arrays. Analysis and evaluation of these
- 4. preclosure radiation safety and the effects of seismic. data are ongoing using codes and models developed for the ity on the surface and underground facilities, purpose. Instrurnent arrays have been installed at depths to 420 m in the shaft and several thermomechanical response The top-level strategy focuses strongly on the investiga. experiments are planned to be conducted on the 440-m level.
tions of the charactenstics of the flow in the unsMurated zone, relying heavily on the current view that the percolation flut is 4. Instrumentation development related to this test work low and that ti.e watar in the unsaturated zone is tightly con. has been ongoing for several years. Innovative instrumenta. fined within the rock matrix. If these concepts can be con- tion has been developed to overcome inadequacies in the areas firmed, then the gertral objective for tL: system and for the of stress measurement and fracture displacement measure. postclosure performance of the enginected and natural barrien ment. An example of this is an extensometer under develop-are very likely to be met. Therefore, the investigatsnt of these ment that measures lateral (shear) movement and rotational concepts have the highest priority in the program. As part of mosement in addition to normal movement in fracture planes. these investigations, the program will address ahernative con. 5. Experience gained by RTP staff and contractors cepts including flow in fractures, later?' movement of water includes participation in the design, construction and opera. at rock interfaces in the unssturated zone, and the effect on tim of a s#4w M pdWy in W dif5Mt area the flow of structural features, such as faults. The ability of of integration of construction, testing, and characterization the unsaturated rock to hold wcter and limit contact of water activities. Transferable technology includes innovative shaft with the waste packages will also be investigated, construction methods and equipment such as the design and operation of the multideck sinking stage, jumbo drilhng, mechanical raise boring, and characterization activities utiba.
! 5. Technology Trartsfer from the U.S. DOE / ing stereophotography for shaft mapping.
AECL Cooperative Project, Richard C. Baker (DOE, Argonne)
- 6. Characterizing Plutonic Rock Sites for Two main areas of technology transfer exist, one of which Nuclear Fuel Waste Disposal, C, C. Davison, is between the United States and other countries, in this case X. W. Dormufh, S. H. Whitaker (AECL IVhife-technology is shared or transferred by joint ventures, or coop. She#-Canada) erative or bilateral agreements.
- The United States takes either an active role as in the U.S. The Canadian Nuclear Fuel Waste Management Pregram Department of Energy (DOE) Atomic Energy of Canada Ltd. is currently amessing the concept of disposal of nuclear fuel 3
(AECL) Cooperative Agreement where penonnel participat' waste deep in plutoruc rock formations. One of the primary directly in the deselopment of transferable technology, or a objectives of the Canadian program is to deselop, evaluate, more passive role as at Stripa where there is no direct involve. and demonstrate methods for characterizing the physical and ment at the experiment level and technology ts transferred in chemical properties of potential disposal sites to produce reli. the form of documented results. able engineering designs and performance assesstnents of the The second area of technology transfer is between U.S. disposal systems. Transport in groundsater at the site would j high. level waste projects. This includes technology transfer be the primary tr=chanism that could bring any radionuclides from the Repository Technology Program (RTP) to a first released from the deep disposal vault to surface during the repositcry project such as the Nesada Nuclear Waste Storage hazardous lifetime of the waste. Consequently, emphasis is investigations (NNw SI). placed on rock mass charactenzation methods that identify Areas in which the RTP is developing transferable tech. features that are potential pathways for radionuclide migra. nology and has the espertise and resources to assist the tion; quantify the hydrological and geochemical properties NNWS! in resolving issues including the following; that control groundwater flow and radsonuclide transport; and
- 1. A test facility exists in Mar ioba. Dinada where coop. determine the geomechanical propert es that control the exca.
crative technology development between the DOE and AECL vauon stabihty and the long. term stability of the rock rnest has been ongoing since 1977. At this facihty, both surface. The information is required at sarious near and far field sur j based tests and undtrground experiments are conducted at the scales, ranging from the order of a metre, near the potenpal Underground *desenteh Laboratory, at depths representatise location o' waste packages, to the order of several hundredi ! of a U.S. reposnory (up to 800 mk The research is genene and of square kilometres and to depths exceeding 1000 m at poten- ' applicable to any hard, ftarc$ and/or stressed rock Cur. tial disposal sites. The methodology being developed conosts tently, technology is being developed in the areas of fracture of field and laboratory tests, vi situ monitoring, and mathe. flow, thermomecharucal response, stress rneasurement, w aste matical modehog and interpretation. The result is a descrip. package and backfill materials research, scabng research, shaft tion of nie charactenstics in quanutatne and quahtauve terms, f i i
_ _ - _ . _ _ _ . . m _ _ . . _ _ - Characterization of High-Level Waste Sites 183 i which can be used to support engineering designs, licensing - developed and/or tested. In particular, the development of , I applications, and environmental and safety assessments. single borehole and cross. hole radar measurements has at. , Atomic Energy of Canada Limited (AECL) has been car. tracted considerable attention. Other developments include the , rying out geoscience field research since 1978 at four plutonic seismic cross-hole technique, sinusoidal hydraulic cross. hole ! rock research areas on the Canadian Shield to develop and measurements, migration experiments using sorbing and non. . demonstrate the various site characterization methods. The sorbing tracers, etc. Some of these methods hate already t:en i early research at the Chalk River. East Bull Lake, Atikokan, tested at other places in Sweden or elsewhere. and Whiteshell research areas was initially aimed at develop. Phase 3 of the Stripa Project started in 1986 and will con. - l ! ing methods to measure the physical and chemical parameters tinue to 1991. This phase is devoted to an integrated valida. . at a stnall scale (within indiudual boreholes and fractures), tion experiment where the various methods previously Since then the program hu evohed in two directions: first, developed are used to characterire a 125. x 125. x $0-m so- l i- called virgin rock body. The experiment is conducted in five tomt.rd developing methods for determining these parameters 4 at the larger regional scale that is relevant to assessing the steps: safety of a potential nuclear fuel waste disposal site; and sec. ond, toward developing methods to evaluate near. field I. preliminary characterization of the rock changes in the rock mass caused by the construction and oper. !
- 2. preliminary predictions ation of a disposal facility.
The most extetsive research area is the Whiteshell Re. 3. detailed characterization and preliminary validation search Area m southern Manitoba, Canada, which includes
-the site of the Canadian Underground Research Laboratory 4. detailed predictions (URL) and AECL's Whiteshell Nelear Resestch Establish. . eta e na ab.on.
ment. The construction of the URL in a previously undisturbed tranite pluton, the Lac du Bonnet batholith, has provided The final step willinclude the excavation of a validation AECL researchers wit h a unique and valuable opportunity to drift and enaking in-flow measurements and tracer expentnents validate the site characterization rnethods at the near field to determine the groundwater now patt:rn around the drift.
. scale and also at, a far field size 1: ale that is somewhat smaller In conjunction with integrated expeiirnent, phase 3 also -
than that of a disposal vault. Recently, geoscience field work includes several developrnent tasks for improvement of site has been expanded outward from the URL to encompass a characterization methods and concepts. The fahwing should much larger reponal-scale area tnt; will permit the character
- be mentioned; iration methods to be demonstrated at a far. field sits scale that is more relevant to assessing the long-term safety of 1. development of high.rtsolution, directional radar potential nuclear fuel waste disposal sites.
- 2. impro ement of techniques for high resolutior borehole seistmes ,
- 7. Site Characterization Activities at Stripa d$tjnPment of three-dimensional fracture network end Other Swedish Projects, Per Eric Ahlstrdm 4 experiments n fracture channeling now (SKB-Sweden) !. estimation of fracture length and aperture from smgle-INTRODUCTION fracture packer tests.
The nuclear pJwer program in $weden consists of 12 reae. tors. Up to the year 2010, these units will give rise to some Tile FINNSJON FRACTURE ZONE STUDY ' 7800 tonne of spent nuclear fuel. Present planning foresees that the spent fuel will be stored at the existing interim stor. It is important to broaden the data base and to develop an age facility for -40 yr before final disposalin a geological improved investigation technique to characterize the nuclide repository, Such a repository is planned to be located in bed. transport properties of large fracture zones in future safety i roca and to be in operation from 2020. A siting application assessments. To test and develop methods for deterrmnation should be submitted to the pertinent authorities around 2000, of the pertinent properties in fracture zones, a speial project The application for a siting permit must be based on a sys- wts started in 1984. The main efforts of this project are car-tem adapted to the site and on a comprehensive analysts of the ried out at Finnsjon. + long .erm stfety of the system. To perform such adaptation A subhorizontal tone has been studied extensively at and safety analysis, the site must be carefully characterized. depths ranging from 100 to 300 m. The zone is -70 m wide f During the 1990s, therefore, we p!an to select and character- and has a mirumum lateral extent of 500 m. It has a dominat- ' ize at le4st two candidate sites. The characteriration would ' irig influence on grour.dwater now Saline groundwater of take ~$ yr at least and should therefore start about 1993. -5000 mg/l chlorine is found below the zone, whereas the Before starting any detailed site inmtigations, the methods to w ster above the zone is fresh. This indicates that the zone at ! be used must be developed, carefully tested, and verified. A least in part constitutes a hydraulic barrier against descending great part of the ongomg research in Sw&dG is devoted to fresh water, these tasis. This paper gives a few examples of projects that Interference tests have established hydraulic connections are of gr(at importance in this respect. witbin the zone between four boreholes at distances up to 450 m. An additionalinterference test is planned for 1988. Preliminary tracer tests using the nonsorbing tracer ura, THE INTERN ATION AL STRIPA PROJECT nine have shown that it ts possible to obtain quite a satisfac-The international Stnpa Project is an Orgamzation of Eco. Iory breakthrough curse in a borehole 440 m aw ay from the nomic Cooperanon and Devekipment/ Nuclear Energy Agency injection hok. The first arrival occurred after 37 days under sp(msored project conducted at Sinpa, Sweden at an abu.- a gradient of -0.004. Work on further tracer tests started in t doned iron mme. A connderable part of the project has bren late 1987. These tests include three different terhr.iques: radial and is still devoted to the development of various methods for flow, dipole flow, and flow under natural gradient at distances [ characterizing rock Through phases I arad 2 of the prof eet, up to 500 m. Great care must be exercised in selecting proper tracers for these tests in order to obtain meaningful data, garious geophysical and geohydrological methods hwe been i [ wrT -"F--
l 190 Characterization of High Level Wasto Sites Tile SWEDisil llARD ROCK L4IsORATORY fusion, scales of centimetres, milhmetres, and less becorne of interest. The ongoing research prograrn in Sweden tries to The studies exemphfied above are directed towards specird address the various phenornena mvohed in these various scajes features, or rather lirmied parts, of the bedrock. A repository to a pr per way. The goalis to carry out the necessary detailed for spent fuelin Sweden wiu need a rather large rock volume site characterization work on a specific sites from 1993 and cosenng an area of -l km .2 It will thus be necessary in chat- onwards using tested and sufficiently validated methods. acterize the rock over several squ;.:re kilometres at the re- Then, it shouM be possible to submit a siting bcense applica-pository Site to be able to make a detaPed assessment for or a spen ud reposhory on a spdc site by W year long term safety. The methodology for such a large-scale chst-
- acterization wiu be tested and further developed in connection with the construction of a nes underground research labora-tory caUed the Swedish Hard Rock Laboratory. This projee: 8. HLW Site Characterization Plan in Switzer-started in late 1936 and the laboratory is planned to be auh- land, M. Thury, C, McCombic (Nagra-Swi4er-able for espertments at 400- to 500-m depths in 1993 and wiU then replace Stnpa as the main site for ur pru experiments. I##dl it has been proposed to iocate tne laboratory m the vicm. TM Swin concept for high-level waste IllLW) disposal i
it) of the Oskaahamn nuclear pov,er plant, where the CLAB is based on the fobowing imponant premises (a) Spent fuel intenm spent nuclear fuel storage is also situated. This area from a re;atively small nuclear power program is reprocessed has the proper infrastructuie for such a research facihty and in facilities abroad;(b) the vitnfied waste wiU be returned to the geology was also known for the previous construction Switzerland where an intermediate storage period of -40 yr projecis to be of potentialinterest for a deep underground lab- allows adequate decay of radiation and heat production; oratory. The work up to 1993 is divided in two main phases: potential sites are bemg selected and charactented in the the preinvestigation phase and the construction phase. Botb northern part of the country where varied sedimentary strata phases me!ade considerable collecuon of geological, geophys" he dove enstalline basement rocks; and (c)if the decision to cal, and geochemical data, conceptual and piedictive model- implement nanonal disposal facilities is taken towards the und itig, and evaluation of predictions. of the century, a shaft accessed mined repository will be con-The preinvestigation phase is goia on in three neps: stmted in a suitable host rock at a depth of up to -1200 m. localization, site desenption, and prediction. The locahzation The procedure chosen for site selection and characteriza-step aims at a regional description of the important geologi- tion involves three distinct phates of investigation, Phase 1, cal propernes et the bedrock, Geophyucal meamrements from wl.ich commenced in 1980 and is stiD continuir g, is a regional the air and from the ground in cornbination with geological in5est Fation includmg single deep-borehole programs at a mappmg, tectonic studies, and topegraphic stu6es were used number of sites heven or eight) spread actors aa area of to identify a number of potentially mteresting sites. On a few ~1200 km2. This part of the program has been strongly in-of these a nurnber of 100- to 150 m-deep percussion dtdlec fluenced by a parauel regulatory authortry requirement to pro-ooles were rnade for pumpmg tests and for groundwater sam- duce a comprehensne feasibihty project (Gewkhr) based on pimg. In addition, a few deep cored holes were rnade. fiased real field data. Important consecuences of this requirement for the laboratory have been (a)to enforce an early concentration on a specific on was the data selected. Thethus couccted, site description phaseaw1 specific sit (11 include option extensqe for detailed study On practice a deep repository in rocasurements in deep boreholes at the se!ected site. It is granitic rock) and (b) to necessitate in-depth single hc4 test planned to have enough data to be able to confirm the suit- programs that produced detailed field data in quantities and abthty of the site sebeted by the end of 1988. Data will be col- in quahty beyond the objective requirements of an early ste lected to facihtate a detailed site description and a numerical reconnaissance phase. rnodel of the groundsater regime,. A large4cale pumping test The second phase of the siting prc grarc will b based on will be conducted and the numencal model will be esaluated selection of one or more local sites (-10 km8 in area) for against this test. more detailed characterization from the surface. The second The construction phase is expected to start in 1990 and phase, which can commence onl> after the final analyses of includes the excavation of a tunnel down to 400- to 500-m phase 1 data in 1990/91, can include study of crystallir. depth, it has been concluded that a tunnelis preferable to a and/or sedimentary socks. However, the technical capacity vertical shaft for vanous reasons, e s., the tunnel eives access available in 5*,t:erland is restneted. particularly in view of the to a much larger part of the rock and the possibihty of recognized need to press ahead with other more urgent pro-excasating special drif ts to study special features without dis- grams for gaological dnposal of low level waste. Accordmgly, turbing the further construction is much bet'.cr. The difference the most appropriate procedure is cenainly a sequential HLW in costs between the tunnel and shaft ahernatives ts rather mec tes prom invching successive sites until smau for t'e depths considered. For ventilation and a,no for an acceptable option that promises to be capable of hosung transport of personnel, a shaf t will also be built, but this can a demonstratably safe facility is identified. The t me i scales be constructed trore easily after the tunnel is asailable' fx HW repository operation (af ter 2000) also permit this Throughout the connruction phase, extensive data wiU be col-
*IP' lected to check and update the predictive models. The question of wben there is sufficent data to dernon-strate adequate safety is, of coun.e, erucial. C ologicalinput CONCLt' DING HDtARKS to a fmal safety assessment for bcensing repontory weranon it is iraportant fer the safety analysts to understand ad will be required %m a site characteruation invohing invr to be able to model the bedrock surrounding the repoutory i., tigation at depo. .sm shafts anc' galleries. This phase vi different geometncal scales. A regicnal scale of the order os exploration from underground const:tutes phan til of the SW0 m is perur,ent f or locahz'ng potential regional iones witt Swiss charactenratwn pian; accordmg to curren p!annms, high transndssvity ar&or rosnbie mosements. A scale of the phase !!! can commence at the carbest in IVC and should be tacer of 500 m is requi+cd f or the layout and design of the compleird by 2010, repository. A scale of the order of 50 m is pertment for At ali stages of site charactenratior. work programs ir.
desabing maior sananons m "bulk" flow of groundaater. Switteriand are directly affected by the specific lepslatsor,' Tt.nr els and u.afts may hase an influence on ground *ater d:s- introduced in 194 to coser esen preparatory work for geo-tribution. Analysis of such phenomena must be rnade in a logic durosal projects. As a coraequence of the formal pro-scale of -5 m. In the ena?yss of c.'tannebris and of matru dif- cedures invohed m applyms for site ins est:ganon permits, ice i i
L l 2 f,' s f Characterization of High Level Waste Sites 191 t h rropams must be specified in advarr at a rather detailed quantitatively from those for HLW because of the lower tox-oct More importantly, however, the complex legal structure icities and shorter time scales associated with LLW: but, the [ basi: issues to be clarified are common. Therefore, deliberate nn lead to long delays resulting from localized opposition, efforts are made in Switzerland to encourage the transfer of {( r,en for geologic research work with no specific siting com-emmer t. An extreme example is the case at one deep borehole information between the corresponding disposal programs and I( ue where the necessary permission of the Federal Council of to baild b th on a common pool of technical expertise. [. %nisters was granted in 1982,2 yr after submission of the j arpbettion, but delay in local permitting has prevented work 1. H. ISSLER, C. McCOMBIE,"Demonstracon of the Feasi- ! commencing up u now (beginning of 1988). bility of Safe Disposal of Radioactive Wastes: The Swiss E The key issues to be addressed in a site characterization Approach," Proc. Symp. Waste Afanagement. Tucson,
;regram have been discussed at length in many countries, in Arizona, March 24-28, 1985.
the paper, we comment only on technical aspects; the socio- 2. "Nagra Feasibility Study-Projekt Gewihr 1985," Nagra pohcal and economic issue, are much more country-specific. Gewihr Reports NGB 85-01 to NGB 85 08, Nagra, Baden. In Switzerland, there are no specific regul tory guidelines with Switzerland (1985). Jetai! reqirements for HLW vte characterization. The safety authorities issue only global safety goals to be fulfilled by the 3. "Verordnung Ober Vorbereitende Handlungen im Hinblick naal disposal system.' From the project side also, a rigid sys- auf die Errichtung ei,es Endlagers fnr radioaktive Abfalle tem of requirements has not been developed. Instead, the pro- vom 24. Oktober 1979," SR 732412, Berne, Switzerland trams are, in principle, derived in collaboration between safety (1979). a3sessors who specify data requirernents, carth scientists wh Schutzziele fut die Endlagerung radio-derive investigation programs to satisfy these, and field geol- 4. gygg "Richt'Jne R 21. Kommission for die Sicherheit der Atom-opsts and site engineers who finalize and execute the site anlagen (KSA)/Hauptabteilung for die Sicherheit der work. The objective of this system is to produce optimized, Kernanlagen (HSK) (1980). project-specific programs that will yield all those data (ar* only those data) that are needed for proper system perfoi 5. C. McCOMBIE, A. L. NOLD, M. THURY, "Swiss Field mance assessment and for engineering design. In practice, the Investigations for Radioactive Waste Repositories," Int. boundary conditions on the work,in particular the political Symp. Coupled Processes Affecting the Performance of a
;cessure and si. ort time scales of the "Gewihr" project, have Nuclear Waste Repostrory, Berkeley, California,1985.
led to programs going far beyond this optimized minimum. 6. M. THURY, A. GAU TSCHI, "Testing Progmmme in The components of the deep borehole testing Deep Boreholes Drilled in Sediment Covered Crystalline have been surnmarized. in previous pubbcations, and theprogramRocks in Northern Switzerland," Proc. 2nd Int. Conf. planned optimization for future work has been discussed. Radioactive Waste Afanagement, Winnipeg, Manitoba, Most effort has gone into study of site hydrogeology, smce Canada,1986, long-term release by groundwater transport is the normal sce-nario. Accordingly, there have been rnany measurements of the usual parameters (heads, transmissivities, water and rock chemistry, etc.). Furthermore, work to date has led us to rec-9* Characterization Pro 9 ram for the Gorleben ognize the extreme importance of specific points, such as the Site in Germany, Horst Schneider (Phys-Tech following: Bundesanstalt-FRG)
- 1. Detailed characterization of fine. scale flow systems is Since the early 1960s, the radioactive waste disposal poucy necessary because of their high impact on nuclide transport. in the Fede;al Republic of Germany (FRG) has been based on
- 2. A good understanding of the behavior of radionuclides the decision that all types of radioactive waste are to be in the geosphere is important because this determines the dispomi of in the deep subsoil, priority being given to the dis-retention potential at long times when near field enginetred posalin rock salt formations, barriers no longer retain their integrity. The fourth amendrmnt of the Atomic Energy Act of 1976 i.: Section 9a obligates the federal government to set up instal-
- 3. The specification of parameters to be measured must be lations for the disposal of radioactis 3 waste, rneaning that the accornpanied by justified requirements on accuracy. Efforts disposal is a national task. Accogiing to Section 23, the to achieve unnecessary accuracy in hydrologic tests or in water Physikalisch-Technische Bundesaffstalt (PTB) is charged with enalyses, for example, can swiftly result in lengthy and overly the execution of this task.
expensne testing procedures. A step towards the realization of a repository was the
- 4. It is important to be able to predict or attrapolate system announcement of the "Safety Criteria for the Disposal of behavior in space and time. Therefore, borehole test programs Radioactive Waste in a Mine"in 1983 by the Federal Minis-are complemented by regional geophysics, hydrochemistry, ter of the Interior, at that time responsible for nuclear safety and neotectonic studies. and radiation protection. These criteria, summarizing experi-ence and knowledge in the field of radioactise waste disposal Because the emphases in geologic characterization for dis- so far acquired, essentially emphasize that no universally valid posal facilities are not identical uth those in conventional quantitative enteria can be given. Rather, the required safety exploration work, it is valuable to have a test bed available for of the repository mus- be proven by a site-specific safety specific deve pment tasks and as a practice .round. In Swit- assesstr'er.: for normal repository operation, for incidents in zerland, tha , st bed is provided by the underground rock lab- the operational phase, and for the postoperational phase, oratory at the Grimsel site. Here, testing tools for hydrology which takes into account the whole system "geological condi-and geophysics can be tried out and methods can be devel- tions, mine, waste product." They are instructions that must oped. In particular, efiorts are devoted to development of be complied with by the PTB and be observed by the licens-geophysical approaches for nondestructive characterization of ing authonty. These instructions forrn the regulatory base, in a rock mass (e g., seismic or radar temography). addition to the directly applicable Atc.mic Energy Act, which Finally, it should be stressed that we see a strong connec- stipulates the essential licensing requiremut, namely, the nec-uon between the charactenzation requirements and techniques essary provisions against harm according to the state-of-the-at potential HLW sites and those at sites for geologic reposi- art technology. Regarding this, the required standards will be tories for LLW. The requirernents for LLW projects differ put m concrete terms by analogously appl >iag the standards D. mO
, . _ . _ . . ___ _ -. -_ _ _ m - _
192 Characterization of High Level Waste Sites of the Radistion Protection Ordinance and guidelines of the exploration by mining, since a sufficiently complete picture of competent Federal himister, the internal dome strucmre cannot be obtained solely by mea-
. Since 1979, the Gorleben salt dome, situated m the north- sures aboveground, because, following the safety enteria, the eastern part of the FRG, has been investigated as a candidate test borings from the surface roust be limited to a minimum repository site for all types of radioactive waste, especially to maintain the functional capability of the natural barriers.
heat-generadng waste. The objectives of the investigations and Accordingly, the focus of the work performed at the site the requirements concern 6s the site characterization program, Lts now shifted to shaft sinking. After the two shafts have essentially derived from the safety criteria, are to provide all been sunk, corresponding to the planning, drifts of ~25 km necessary data for the site-specific safety assessment, the com. in length will be driven for the underground exploration. In plete documentation of geological data, and the pertinent addition, a total of -120 km of pilot and reconnaissance holes information for the detailed layout and optimization of the will be drilled towards the sides and the interior of the salt disposal mine as well as the safe operation of the repository, dome, including some deep-core hole drillings. Apart from ascertaining the overall geological situation, The geological work will be concentrated on locating drifts the task of the exploration program is, for instance, to dem. and reconnaissance holes, mapping of the faces in the shafts onstrate that suitable and sufficiently large rock salt volumes and drifts, core logging, and determination of the chemical are availabic, considering adequate safety pillars between dis- and mineralogical composition of the salt rock and of the posal panels and unfavorable strata such as anhydnte and pot- chemical composition of solutions and gases. Geophysical ash seams, as well as between the underground openings and prospecting mainly involves the use of electromagnetic reflec-the boundary of the salt dome, tien and geothermic roethods. Extensive work will be required Extensive exploration from the surface comprising numer- for the geomechanicalinvestigation and surveillance of the salt ous prospective drillings and seismic measurements has been dome and of the mine openings. In this respect, laboratory almost completed. On the base of the achievements gained by and in situ tests will have to be performed. research showing that rock salt is a favorable host rock for The underground exploration of the salt dome's interior reasons of its thermal conductivity and mechanical behavior, will be carried out at a depth of 840 m, which is -30 m above the extremely low permeability fc- liquids and gases, the the planned disposallevel. The drifts of the exploratory mine absence of groundwater (apart from brines)in rock salt for- will later be used for ventilation purposes. mations, the advantages with reFard to minag, and the large The site cl'aractes:zation aad assessment at Gorleben is' rock salt occurrences in northern FRG, the investigation expected to last several years, after which the license applica-results so far available have confirmed the salt dome's suit- tion documents will be prepared and submitted to the licens-ability for a repository. Consequently, in 1983, the federal ing authority. It is scheduled to start up repository operation government approved tne commencement of the subsurface around the year 2005. G y e l ~j l
;I 1
~ _ _ - _ _ - - - - - , - - - - - - - - .
h/ 207 TUFF CHARACTERIZATION ACTIVITIES-l Cosponsored by the isotopes and Radiation and the Fuel Cycle and Waste Manage nent Divisions Session Organizer: J. C. Laul (PNL) All Papers invited Site Characterization at Yucca Mountain, utilized in continued performance and design analyses. Fur.
- 1. ther switivity studies utilizing the improved data base can Maxwell B. Blanchard, Ue/ S. Clanton (DOE, Lay then be conducted and confidence levels for key geotechnical Vegas >, Donats u. Atexander, Caroi t. nanton parameters can be re.~tned.
(DOE), Jean L. Younksr, Michael D. Yoegele (SAIC, Las Vegas)
- 2. Stratigraphic and Structural Framework of ne Yucca hf ountain site. located in south-centralNevada, Yucca Mountain, Nevada, R. W. Spengler, K. F, has recently gained a central postuon m the 11.S. geologic Fox, Jr. (USGS) repository program. The recent choio of this site as the only potential repository site to be characterized makes it increas' Yucca Mountain is located within tne southwestern mgly important that the activities to be conducted dunng site Nevada volcanic field, -140 km northwest of Las Vegas, characterization are both adequate and sufficien: to obtain the Nevada, and 50 km northeast of Death Valley, California.
sue data required to de :ne the hcensability of the Yucca The mountain consists of a series of long, linear, north. Mountain site. Thi;'. ularly true f'or acuvities with long trending volcanic ridges that approach an 190-m maximum lead tim,es,of requirits < periods of data acquisition. eleva ion near The Prow (Fig.1). The broad intermontane
, Prehmmary eit~specu e data requirements are presented alluviated valleys of Crater Flat, the Amargosa Desert, and m,the site charr . uzation plan (SCP) for the Yucca Moun- Jackass Flats, averaging 800 to 1100 m in elevativa, form the tam site. The a 4,oach used to establish the data needs rebes western, southern, and castern margins of Yucca Mountain, on a set of performance and design issues denved directly respectively. North of The Prrw, Yucca Mountain merges from the U.S. Nuclear Regulatory Comnussion's performance with other volcanic hiehlands that flank the southern rim of and design requirements in 10CFR60. Strategies I;or demon- the Timber Mountainhasis Valley caldera complex (Fig.1).
strating compliance with performance and design issues were developed and are presented in the SCP. An integral part of STRATIGRAPHY the strategy for each issue is a prelimmary identificauon of the site-specific data base required for evaluating regulatory Sedimentary strata, buried beneatn a thick volcanic cover at Yucca Mountain, consist of highly folded and faulted 300-compliance. At the currut level of maturity of the program, the confidence levels indicating how much information is to 600-million year-old Paleozoic and upper Proterozoic needed about a given parameter are generally qualitative. With rocks. These rock units, exposed at Bare Mountain and the maturatica 3l the program, performance and design-related Calico Hills and intersected at a 1250-m depth in dr01 hole sensitivity analyses will provide increase definition of the im- UE 25p No.1 (Fig. 2), are p'redominantly timestones, dolo-mites, shales, and qnrtzites. The Miocene volcanic section, portence of various site parameters, so that confidence levets can be made more quantitative. in places more than ISM m thick (Ref 3), contains mainly rhyolitic ash-flow tuffs intercalated with volcaniclastic sedi-The goal of the repository is to prot'ect the safety and ments. The ash-flow tuffs consist of an alternating sequence health of the public for a period of 10000 yr. The data-base and confidence levels must be developed in a menner consis- of partially to deusely welded rock that records a complex his-tent with this goal. However, there are no standard criteria tory of emplacement, compaction, cooling, crystallization, and that can be used to determine the confidence level required for alteration of hot gaseous flows of pyroclastic material. Most a given parameter in order to ensure public health and safety, of the pyroclastic material erupted from source areas near the This is in part due to the interdependence of many of the site margins of the Tirnber Mountain. Oasis Valley caldera complex between 11 and 14 million years ago. Rocks in the lower part parameters important to repository performance. The process for refining confidence levels must be iterative in that perfct-of the volcanic section (Lithic Ridge Tuff; Tram, Bullfrog, an<i Prow Pass mernbers of the Crater Fiat Tuff; and tuffa. mance and design analyses can initially be used as a screening ceous beds of Calico Hills) are mostly porous, partially weidad tool to eliminate pararneters from consideration if they can be shown to have little or no potential impact on repository per- tuffs that have been pervasively altered to clays and zeolites.' formance. The parameters required to predict the range of The overlying Topopah Spring rnember of the Paintbrush variation in geologic conditions that is likely over the next Tuff varies in thickness from 250 to 350 m across Yucca Mountam aad dominates that part of the geologic section 10000 yr and the information necessary to estimate the prob-above the wster table (Fig. 2). The member is composed of abilities of catastrophic geologic events must ba obramed and m
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Y' e z.s s s.s nousuns 36'40' OUATERNARY ALLUVIUM h OUATERN ARY B ASALT AND CINDER CONES TERTIARY VOLCANIC ROCKS h PALEOZOIC AND UPFER PROTERO2OIC ROCKS f FAULTS THAT OFFSET QUATERNAf'Y DEPOSITS. I BAlt. AND B AR ON DOWNTHROWN SIDE. I, DASHED WHERE .:NCERTAIN, DOTTED WHERE g CONCEALED, OUERIED WHERE INFERRED DETACHuENT STRUCTURES, DOTTED WHERE CONCEAL.ED. TEETH ON UPPER PLATE Fig.1. Geologic map of Yucca Mountait, Nevada, and vicinity, showing selected faults: TM, southern rim of the Timber Mountain-Oasis Valley caldua complex; R, proposed repository (modified from Ref.1). hard, bnttle, finely crystal!ine, densely welded, highly frac- STRUCTURE tured pyroclastic material that formed through coeval coolin5 of several ash flows emplaced in rapid succession. Excavation The volcanic strata at Yucca Mountain are broken into a of an underground radioactive waste repository is being con. series of 1. to 4.km. wide fault bounded blocks that are til.ed sidered within the Topopah Spring near the central part of 5 to 15 deg eastward and southeastward and bounded by Yucca Moentain, where the base of the member is more than westward-dipp ag high-angle faults. Along the western edges a hundred metre < abose the water table (Fig. 2). of maje bck.s, faults form highly brecuated zones as wide I. _
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-600.3 STRATIGRAPHIC BOl#OARY TO TOTAL DEPTH TD-3b5m Fig. . . Fence diagram along sect.c A '.'(Fig.1), showing .tratigraphy u selected drill holes at Yucca Mountain.
as 500 m and displace strata as mun as 400 m. The central County, Nevada," Open-File Report 84-788, U.S. Geolog-parts of blocks iemain relatively unt ited. u crer, the east- ical Survey (1984). ern margins are characteristically - oy an abundance af 2. M. D. CARR, S. J. WADDELL, G. S. VICK, J. M. nearly parallet, west-dipping f-, ., each of which displaces STOCK S. A. MONSEN, A. G. HARRIS, B. W. CORK, strata by only a few metres. Strata between these nearly par- F. M. BYERS, Jr., "Geology of Drill Hole UE25p#1: A allel faults progressively steepen eastward toward the extreme Test Hole into Pre. Tertiary Rocks near Yucca Mountain, eastern edges of blocks. Geometric characteristics of block- Southern Nevada, Open. File Report 86-175, U.S. Geolog-bounding fault zones, as described above, have been postu- ical Survey (1956). lated as titt near-surface mamfestations of gently dipping structures that may extend several kilometres beneath Yucca 3. R. W. SPENGLtR, F. M. BYERS, J. B. WARNER, "Stratigraphy and Structure of Volcanic Rocks i1 Drill Mountain.s At two lowlities near Yucca Mountain (northern Hole USW-Gl Yucca Mountain, Nye County, Nevada," end of Bare Mountain and in the Calico Hills: Fig.1), a low-angle detachment fault coincides with the contact between the Open-File Report 81 1349, U.S. Geological Survey (1981). Miocene and Paleozoic sections. Future geologic studies will 4. R. B. SCOTT, J. BONK "Preliminary Geologic Map of attempt to determine if such faults extend beneath Yucca yucc, . fountain with Geologic Sections, Nye County, Mountain, and, if present, their potential effects on the hydro- Nevada " Open-File Report 84 494, U.S. Geological Sur-logic and tectome regtmes, y,y (g934),
- 1. W. C. SWADLEY, D. L. HOOVER, J. N. ROSHOLT, 5. R. B. SCOTT, J. W. WHITMY, "The Upper Crustal 1984. "Prelimi;ary Report on Late Cenozoic Faulting and Detachment System at Yucca Mountain SW Nevada "
Stratigraphy in the Vicinity of Yucca Mountain, Nye Geol Soc. Am. (bstr. Prog., 19, 5, 332 (1987). I w w
o 210 Tuff Characterization Activities-l
- 3. Neotectonics and Volcanism at Yucca an area to the southwest in which both strike-slip faulting and Mountain and Vicinity, Nevada, Kenneth F. Fox, extensional faulting are important. Post-il million years Jr. (USGS), Michael D. Carr. (USGS, Menlo Park) b* P'.esent (m.y.B.P.)-tectonism at or near Yucca h1oun-tain has involved volcanism, oroclinal bending, extensional Yucca hiountain is located within the Walker Lane belt, faulting, and strike slip faulting.
a northwest-trending zone of oroclinal bending and strike-slip The youngest volcanism in the Yucca hfountain area faulting that divides the southern Great Basin into two parts: formed Quaternary basalt flows and cinder cones (Fig.1). Lit-an area to the northeast dominst'ed by extensional faulting and tie Cones, Red Cone, Black Cone, and an unnamed cone 116 *3 0' 116'15'
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i i - .'i uo-m as LATHROP WELLS CONE , . QUATERNARY ALLUVIUM OVATERN ARY BASALY AND CINDER CONES l l TERTIARY VOLCANIC ROCKS 1 E PALEOZOIC AND UPPER PROTEROZOIC ROCKS f FALlLTS THAT OFFSET OUATERN ARY DEPOSITS. I BALL AND B AR ON DOWNTHROWN SIDE. I. DASHED W54ERE UNCERTAIN. DOTTED WHERE n" CONCE ALED. OVERIED WHERE INFERRED DETACHMENT STRUCTURES DOTTED WHERE CONCEALEO. TEETH ON UPPER PLATE Fig.1. Geologic map, Yucca hiountam, Nevada, and vicinity, showing selected faults: R, proposed repository: SF, possible location of Surface facilities (modified from Ref.1).
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Tuff Characterization Activities-l 211 erupted -1 m.y.B.P., forming a northeast. trend'ag alonent County, Nevada " Open-File Report 84 788, U.S. Geolog-crossing Crater Flat. Lathrop Wells Cone, to the southeast of ical Survey (1984). Crater Flat, apparently was formed in several eruptive stages
<250000 yr ago. These volcanic rocks are part of a diffuse 2. B. M. CROWE, W. J. CARR, "Preliminary Assessment
( zone of youthful volcanic centers located in southeastern Cal. of the Risk of Volcanism at a Proposed , Nuclear Waste ifornia and southwestern Nevada. Crowe and Carr2 estNated Repository m the Southern Great Basm," Open. File Report 80 357, p. 6, U.S. Geological Survey (1980). that 14 of these basaltic volcanic centers lie within 25 km of the proposed nuclear _ waste repository at Yucca Mountain. 3. W. J. CARR, "Regional Structural Setting of Yucca
. Yucca Mountain is broken by a cor4mly t tastomosing Mountain, Southwestern Nevada, and Late Cenozoic network of faults, many of which trend north to northeast, Rates of Tectonic Activity in Part of the Southwestern and dip steeply westward. Displacement is typically west-side- Great Basin, Nevada and California," Open. File Report down, dominantly normal, and, on some faults, displacement 84 854, U.S. Geological Survey (1984).
exceeds 400 m. Most of this movement took place prior t 11 m.y.B.P. (Ref, 3). Movement on some faults (shown in 4. J. W. WHITNEY. R. R. SilROBA, F. W, SIMONDS' Fig.1), however, continued into or was renewed during the S. T. HARDING, "Recurrent Quatemary Movement on Quaternary (2 m.y.B.P. to the present). The Windy Wash the Windy Wash Fault, Nye County, Nevada," Geol. Soc. fault,4 km west of the proposed repository, exhibits through Am. Abstr. Prog., 18, 6, 787 (1986). progressive offset of surficial deposits at least seven episodes 5. A. M. ROGERS, S. C. HARMSEN, M. MEREMONfE, of movement during the Quaternary. The most recent episode "Evaluation of the Seismicity of the Southern Great Basin displaced a <10-cm silt deposit,' yielding thermoluminescence and its Relationship to the Tectonic Framework of the ages between 3000 and 6500 yr B.P. The Paintbrush Canyon Region," Open. File Report 87-408, U.S. Geological Sur. fault, whose surface trace lies -1.5 km east of the prospective vey (1987). location of surface facilities, may be the most important in terms of seismic design. The length of this fault is at present
- 6. J. M. STOCK, J. H. HEALY, S. H. HICKMAN M. D unknown, but it could approach or exceed 30 km ifit connects ZOBACK,"Hydraulic Fracturing Stress Measurernents at with the Stagecoach Road fault to the south (Fig.1).
Yuc.ca Mountain, Nevada, and Relationship to the Seismicity in the Yucca Mountain region has been moni- Regional Stress Field,* /. Geophys. Res.,90,8691 (1985). tored smee 1981 by a 53. station network. Six stations are
- 7. W. B. MYERS, "Detachment of Tertiary Strata from located at Yucca Mountain. Results to date indicate that the Their Paleozoic Floor near Mercury, Nevada." Geol. Soc.
current level of seismicity at Yucca Mountam is very low, but Am. Abstr. Prog., 19, 7, 783 (1987). seismicity increases to the east in the Jackass Flats area. On the basis of focal mechamsms, epicentral hneations. snd crien- 8. F. W. SIMONDS, R. B. SCOTT,"Detachment Faulting tation of structural grain, faulting at depths >l or 2 km ts and Hydrotherer.1 Alteration in the Calico Hills SW Nevada," Eos, Trans. Am. Geophys. Union' 68'4[*1475 Judged to be predommantly strike shp on north-trending faults.8 't he distnbution of epicenters, however, shows little II987)~ correlation with known Qaaternary f,n.lts. 9. F. MALDONADO, "Late Tertiary Detachment Faults in Hydraulic fracturing experiments at Yucca Mountain indi. the Bullfrog Hills, Southwestern Nevada," Geol. Soc. cate that the least principal stress trends west-northwest and Am. Abstr. Prog., 17, 7, 651 (1985). that the relative magnitude of the principle stresses is consis-
- 10. R. B. SCOTT, "Extensional Tectonics at Yucca Moun.
tent with the observation that fault movement has been chiefly ta n, SoutLrn Nevada," Geol. Soc. Am. Abstr. Prog., dipalip on north to nor:heast-trending faults. The type of jg*yg gggg* fau! ting at depth, as inferred from focal mechanisms, thus seems to be at variance with that at shallower crustallevels, as inferred from bot,h in stu stress data and from field obser- 4. Characterization of the Subregional Ground- . vations. This could imply decoupb,ng of the shaliow crust at Yucca Mountain from that below. water Flow System of Yucca Mountain and I The contact of the Tertiary sequence with subjacent Vicinity, Nevada-Caillornia, John B. Czarneckr. Paleozoic rocks is 1.25 km below eastern Yucca Mountain. (USGS) This contact appears to be a detachment fault where it sur- . faces north of Mercury,45 km east southeast of Yucca Moun- Tae U.S. Deparvinent of Energy (DOE) has been directed tain,' at the Calico Hills,s at the northern f ank of Bare by Congress to copJuct detailed characteritation of Yucca Mountain, and northwest of Bare Mountain in the Bullfrog Mountain, Nevada, to evaluate its suitability for a mined geo-Hills.' It has been postulated that the north. trending Quater- logic repository for high-level nuclear waste. Although the nary faults at Yuces Mountain are bstric normal faults tnat repcatory would be placed in the unsaturated zone beneath flatten at depth and merge with this or with other detachment Yucca Mountain, an understanding of the regional ground-faults within the Paleozoic and Precambrian basement.d As water flow system is needed in order to (a) assess hydrologic yet. the Quaternary movement on the detachment fault (s) that changes that could occur as a result of potential tectonic pro-is implied by this hypothesis has been neither demonstrated cenes and climatic changes, (b) evaluate the effects of poten-nor refuted. The detachment hypothesis, however, could tial groundwater development, and (c) derme hydrologic account for the apparent variation in faulting style and stress boundary conditions for detailed modeling at the repository regime with depth. There is little evidence that the northwest- site. The U.S. Geological Survey is investigating the regional trenoms structures characteristic of the Walker Lane b6t have groundwater Cow system for the DOE. directly influenced Quaternary or contemporary tectonics at Yucca Mountain is located in the Alkall llat Furnace Yucca Mountain. Such structures, if present, are probably Creek Ranch groundwater subbasin. In this subbasin, water either ceccealed below the upper plate (s) of the detachment in alluvium, volcanic tuff, and carbonate rocks generally flows system or are inactive, from north to south. Hydraulic head ranges from -1200 m above sea level north of Yucca Mountain to ~600 m above sea level at the southern ee i of the subbasin at Franklin Lake
- 1. W. C. SWADLEY, D. L. HOOVER, N.ROSHOLT, playa. Recharge occur i the subbasin north of Yucca Moun-
"Preliminary Report on Late Cenozoic Faulting and tain (-60re) and alons Fortymile Wash (-40re ), a mejor Stratigraphy in the Vicinity of Yucca Mountain, Nye south draining wash about 4 km east of Yucat Mountain. The
a P, - w I 212 Tuff Characterization Activities-l 5. principal area of discharge is at the southern end of the sub- manent storage of high-level nuclear waste. If a license is basin; discharge is by evapotranspiration at Franklin Lake granted, the repository would be constructed in partially satu-r playa (65%) and possibly by spring flow at Furnace Creek rated welded tuff at ~300 m belowland surface. The presence L- Ranch (35%). The distribution of recharge and discharge is of an unsaturated zone that ranges from 300 to 750 m thick, based on the results of two-dimensional, finite eternent, combined with an arid snvironment, is presumed to be a rumerical modeling. major asset in the ability of the rocks to isolate nuclear waste.
- Beneath Yucca Mountain, water flows predominantly in Cherefore, much of the site-characterization effort will focus fractured tuff. The potentiometric surface dips steeply (hy- on evaluating the hydrology of the unsaturated zone. On the draulic gradients as much as 0.2):o the south and east beneath basis of existing data and the general principles of unsaturated the northern and western parts of the mountain, whereas the flow, a conceptual model of moisture flow in this environment surface is almost horizontal bereath the eastern and southern has been developed to guide site cha2acterization.
parts. The steep gradient may be caused by (a) fewer open The unsaturated zone hydrogeologie urits beneath Yucca fractures than in adjacent areas, (b) faults that contain fault- Mce ordst of alternating layers of welded and non-1;ouge seals or that juxtapose transmissive tuff units against w en, . S :lative to the nonwelded tuffs, the welded tuffi nontransmissive suff units, or (c) the presence of a different characteucauy have greater fracture density, much smalier type of lithology that is less subject to fracturing, such as matrix tatunted hydraulic conductivity, and smaller matrix rhyolite or argillite. Alternatively, the steep gradient may be porosity, Structurally, the tuff units dip to the east; the pro-related indirectly to the distribution of in situ stress on the posed repository block is bounded on the -ast and west by rocks. faults: and the block is transected by a major normal fault, the Potentiometric and temperaturs data frorn deep holes . Ghost Dance fault. drilled in the Amargosa Desert indicate a potential upward Average annual precipitation at the site is ~150 mm. of component of groundwater flow (hydraulie gradients of 0.02) which only a small fraction becomes net infiltration. Net from depths as great as 600 m. The concept of upward flow infiltration probably is spatially and temporally variable is supported by convex-upward profiles of groundwater tem- because of substantial topographic relief and the presence of perature plotted as a function of depth, in addition, potectio. surficial units with spatially variable infiltration characteris-metric data indicate tha: a groundwater divide probably exists ties. In the deeper parts of the unsaturated zone, pulses of in the Greenwater Range between the Amargosa Desert and infiltration probably tend to be damped out to produce an Death Valley. Hydraulic bead under the Greenwater Range is approximately constant vertical moisture flux. The conceptual as great as 875 m above seallevel, whereas hydraulic head in model of moisture flow and storage in the unsaturated zone the Amargosa Desert and in Death Valley are ~615 m above hypothesires the possibility for s ertical and lateral moisture sea level and at sea level, respectively. This information indi- flow, capillary barricts, moisture flow in the rock matrix and cates that a reexamination of the conceptual model of regional in fractures, perched-water bodies, and downward liquid / flow is appropriate. The revised model would accommodate water flow along faults. Upward water / vapor transport may the following new concepts: (a) upward flow from great occur within air filled fractures in the welded tuft. Unsatu-depths that probably occurs within the subbasin, possibly rated-rone flux beneath the proposed repository is estirnated from underiving carbonate rocks; ib) groundwater recharge not to exceed -0.5 mm/yr. At this horizon, moisture now l that may occur even in arid areas such as the Greenwater probably occurs predominantly as vertical / downward liquid / l Range and possibly the Funeral Mountains, although other water flow in the partially caturated rock matrix: however, the interpretauons of the cause of the high groundwater in the factors controlling the interaction between moisture flow in area are possible; and (c) groundwater discharge near Furnace fracturm and in the matrix under these conditions are not well Creek Ranen that may be from a separate, deeper, confined understood. t flow system (possibly carbonate rocks), rather than from the Hydrologic characterization of the unsaturated zone be-subbasin in which Yucca Mountain is locsted. If the concep- neath Yucca Mountain will entall approaches different from tual model of the subbasin groundwater Dow system is sim- those used in standard unsaturated. zone or saturated-zone plified by removing the groundwater discharge boundary investigations. Aspects of the characterization that require spe-condition at Furnace Creek Ranch, then a smaller quantity of cial attention include (al eva2uation of the applicability of the groundwater would flow beneath Yucca Mountain than was accepted concepts and theories of unsaturated-zone Dow to the previously estimated. site,(b) development of new Deld and laboratory techniques, l (c) consideration of multifluid fica (liquid / water, water /
- 5. Conceptual Model of Flow and Solute vapor, and air) together with solute transport, (d) recognition that moisture potential and hydraube conductivity vary as Transport in the Unsaturated Zone Beneath comp!ex functions of saturation. (e) development of an under-Yucca Mountain, Nevada, Dwighf T. Hoxie, Bar- standing of the interaction between moisture flow in fractures ney L. Lewis (USGS) and that in the adjacent matrix, and (f) construction and vali-dation of deterministic and stochastic flow models to predict Yucca Mountain, Nevada, is being investigated to deter- the spatial distribution of moisture flux and its probable var-mine its suitabi'uty for a mtned geologie repository for the per- iation with time.
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213 r TUFF CHARACTERIZATION ACTIVITIES-II. Cosponsored by the isotopes and Radiation and the Fuel Cycle and Waste Management Divisions Session Organizer: J. C. Laul (PNL) All Papers invited A Mineralogic, Pettologic, and Geochemical formed toward the end of the major zeoticization episode. Ite 1. last major alteration below the water table occurred at 11 mil-Studies of the Volcanic Rocks at Yucca Moun- lion years ago (an age based on K-Ar dates from illites), when tain, Nevada, for High-Level Waste DisPosai, D. a hydrothermal system was developed in conjunction with the Vaniman, D. BiSh, D. Broxton, F. Byers, B. waning stages of volcanism in the ne..rby Timber Mountain Carlos, S. Levy, S. Chipera (LANL) Caldera. Questions remain regarding the scale of current alter-ation processes and the inference of future alteration from Studies of mineralogy, petrology, and gec<hemistry at a past alteration. candidate high-level waste repository site must address three - primary concerns: (a) possible future geologic events that can CONFLICTS compromise waste isolation, (b) possible conflicting site uses, Discovery of valuable mineral resources at Yucca Moun-and (c) the natural ability of the site to contain radior'uclide tain could lead to conflicts in site use. Minor sulfide mineral-waste. Data are being collected to address these concerns for ization of probable late Timber Mountain age (-11 inillion a potential unsaturated repository location at Yucca Moun- years ago) occurs at Yucca Mountain in association with cal-tain, pevada. The major tuff units underlying the potential cite, bante, fluorite, and manganese minerals, but at depths repository area at Yucca Mountain extend upwa,d from the >1000 m. A full survey for mineralogic or geochemical thick (~450 to 700 m) Crater Flat Tuff (-13.9 milhon years anomalies is yet to be completed. old), through the mformaUy named tuffs of Calico Hills (-25 to 110 m.13.8 million years old)into the Paintbrush Tuff CONTAINMENT (-410 to 425 m,13.4 to 12.9 million years old). The candidate host rock for a high-level waste repository is within the devitri- Simple downward pathways encounter several permeability fled Topopah Spring Member of the Paintbrush Tuff. This and sorptive mineral barriers to radionuclide transport. The entire sequence has been faulted and tilted to the east and is permeability barriers include vitric nonwelded tuffs and their sovered by the Rainier Mesa Member of the Timber Mountain zeolitized equivalents. The sorptive barriers are complex, ruff (11.6 million years old). inclucing abundant zeolites, less abundant clays, and possibly other minerals that may interact with the geochemically com-niex transuranic elements. All reasonably possible transport FUTURE EVENTS pathways must be conridered in order to assess the probable impact of mineralogy on waste containment at Yucca Moun-Deviations from unsaturated conditions and from low tain. Matrix and fracture mineralogy of the tuffs will both be downward hydrologic flux could alter the currently favorable considered in this assessment. In addition, the icng-term sta-estimates of limited interaction between waste and water at bilities of glasses, zeolites, and clays under a low but pro-Yucca Mountain. Current estimates of water flux through the longed thernal pulse (dehydration /rchpfration stability as well unsaturated tuffs predict only a few millimetres of downward as possible phase changes) are important considerations in pre-water passage per year. Nevertheless, the history of recharge dicting the future performance of natural waste containment l and of possible past variations in flux, transport directions
- barriers at the Yucca Mountain site. ,- _
and tr:nsport mechar. isms must be sought in the truneralogic - , .. ,. and petrologie reccrd. The petrologic record above the water .. table indicates no major alteration of the candidate host rock 2. A Conceptual Design for a Nuclear Waste smce -11.6 milbon years ago, although some fracture miner. Re ository at the Yucca Mountain Site, Thomar als (e.g., calcite, opal, and clays) at relatively shallow depths indicate a smail amount of ongoing transport and deposition O. Hunter, Joe R. Tillerson, Aldred L. Stevens in at least the uppermost part of the tuff sequence. (SNL) Lack of alteration in thick sequences of glassy nonwelded i tuffs immediately bstow the candidate host rock, particularly The Nevada Nuclear Waste Storage Investigations project ' in the southern part of .he site, places limits on possible ele. of the U.S. Department of Energy has recently complead a I vation of past water tailes into the candidate host rock. The conceptual design for a nuclear waste repository at the Yucca major alteration obse ved in the deeper unsaturated tuffs is Mouetaia site. This conceptual design supports the site char-zeolitization of glasses within 100 to 200 m above the present acter;. ration program by defining a reference description of water table. The timing of this zeolitization can be placed prior surface and anderground facilities. This reference desenption ( wot.id provide a basis for identifying design-related issue 3 md l to 11.6 million years ago, basco on the pre Timber. Mountain t age of tectonic tilting recorded by geopeta, features that determining the appropriate site characterization activities to
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s CENTRAL SURFACE FACILmES Fig.1. Perspective view of the proposed repository at Yucca Mountain. it is bounded horizontaUy by structural features and vertically obtain needed information shout the site. If Yucca Mountain is designated as the site ie. a ucense application for the first by the requirement to maintain a minimum of 200 m of over-repository, this conceptual design would form the basis for burden within the irregular topography at the site. Additional final design and construction. adjacent areas for potential waste emplacement have also been ne repository configuration described in the recent con- identified. Substantial additionalinformation regarding the ceptual design report' is tailored to the unique features of the configuration and area available for waste disponi will be obtained during the characterization activities at the site. The Yucca Mountain site. The surface facilities are not located lateral extent of the underground openings is -1.5 miles by directly above the underground facilities, but rather are located -l rnile to the east (Fig.1). While this is necessary to 2 miles. More than 100 miles of drifts will be developed in the accommodate the topography at the site,it is also extremely area to support mining, muck removal, waste emplacement desirable because it allows for underground access via ramps, and retrieval, ventilation, underground shops, training. and . resulting in significant operational and construction advan. performance confirmation testing. The drifts will range in size tages. Two ramps and four shafts will conn:ct the under- from 16 to 2$ ft in width and from 15 to 22 ft in height, de-ground facility to the surface. The underground facility is pending on their function. De extraction ratio in the emplace , located above the water table to take advantage of the unique ment panels is -16%. The current design basis allows for a ' total emplacement of 70000 tonne U of spent fuel and high-isolation features of the unsaturated zone. level v'aste. His will result in ~25 000 containers of spent fuel De surface facilities provide for receipt of the nuclear waste from the transportanon system and allow for prepara. and 15000 containers of high-level waste from defense fa-tion of the waste for emplacement..The current concepts cilitit:s and earlier reprocessing activities at the West VaUey include two primary buildings for waste handling. The facihty. smaller, more simpic building will be used for initial opera. The site. specific conceptual design has formed the basis tions and will have limited provision for packaging and mod- for identifying the site-related data needed for the Yucca ification of the waste. This building is designed to accept 400 Mountain site. Future design activities can now focus on ints tonne U/yr of spent fuel and to operate for -5 yr before the grating new site information into the configuration decisions, larger waste. handling buildinig is in operation. The larger design requirernents, and repository performance analyses. building is designed to accept 3000 tonne U/yr of spent fuel. It will accommodate shiprne its by either rail or truck and the 1. "NNWS! Site Characterization Plan Conceptual Design current design basis assumr i a 70% truck /30?e rail (by mass) Report." SAND 84-2641, compiled by H. R. MacDOU-mix. The design is sufficit atly flexible that up to 80fe of the GALL, L. W. SCULLY, J. R. TILLERSON, Sandia waste (by mass) could br re:cived in rail casks. National Labs. (Sep.1987). De operations perft rmed in the surface facility primar. tly will consist of un!ct, ding of the shipping enks. disassem-bly and consolidation of the fuel assemblies, and packaging 3. Deriving a Site Characterization Program of the fuel in containers designed to meet the contamment from Applicable Regulations, Michael D. Voe-requirement of the U.S. Nuclear Regulatory Commission. De gele, Jean L. Younker (SAIC, Las Vegas), Donald containers are then moved to the underground facility by transporter vehic:c3 that are driven down the access ramp to H. Alexander (DOE) the emplacement horizon. The Nuclear Waste Policy Act (NWPA) of 1982 (Public The underground facility is the location where the waste Law 97-4251 assigned to the U.S. Nuclear Regulatory Com-will be placed in a final configuration consistent with the long. term isolation requirements necessary to comply with the stan-mission (NRC) the responsibility for licensing and regulating facilities used for the receipt and long. term storage of high. dards imposed by the Environmental Prote-tion Agency. The ' underground configuration is determined, in part, by the level radioactive wastes. The technical criteria to be used in licensing a geologic repository were promulgated by the NRC f structural setting at the Yucca Mountain site. A primary area of - 1690 usable acres is planned to be used for the repository; as one of these primary regulations,10CFR60. These criteria l
Tuff Characterization Activities-li 215 address siting, design, and performance of the geologic reposi- a few fundamental expectations about the behavior of a tory, as well as the design and performance of the package repository system at Yucca Mountain. A brief explanation of that contains the waste. The NWPA assigned the Environmen- this top level of the strategy is useful for two reasons: It is a tal Protection Agency (EPA', the responsibility for developing simple example of how the detaded strategy was formulated, applicable standards for release of radiation to the environ- and it points out the features of the site on which those fun-ment from a geologic repository. These standards were damental expectations are based. promulgated by the EPA as 40CFR191 and are incorporated The main role of a repository system is to isolate waste for by refaence in 10CFR60. The U.S. Department of Energy a long period. The principal regulation that governs that role (DOE), was assigned the responsibility for developing general is the standard requiring that the system release no more than guide!!nes for the recommendation of sites for repositories. certain stated amounts of radioactivity to that part of the emi. These guidelines were promulgated as 10CFRS 4 and received ronment accessible by human beings during the 10000 yr after the concurrence of the NRC. the repository has been closed. The top-level strategy presented The regulatory approach embodied in the technical criteria in this paper is simply the strategy for demonstrating compli-of 10CFR60 is somewhat different from that encountered in ance with that fundamental release standard. Extensions of regulations for other nuclear facilities. Several of the echni- this top-level strategy show the way that the DOE expects to cal criteria focus directly on performance of the natur 11 bar- demonstrate compliance with other regulations; they are ex-riers, i.e., the properties of the site itself. Furthe more, plained in the site <haracterization plan. 10CFR60 directly addresses the necessity for concern about in developing the top-level strategy, the DOE began by public health and safety by manduing the required lerfor- considering the elements of the repository system that are mance of the natural system for periods of time of up to avsilable to be reUed on for meetmg the release standard. The 10000 yr. A multiple-barrier approach, including both engi- principal way by which radionuclides could move from a neered and natural systems, is incorporated in the 10C;R60 Yucca Mountain repository to the accessible environment is performance requirements. The multiple-barrier approac1 was through the foDowing sequence: slow downward movement of developed in recognition of the fact that reliance solel. on water through the unsaturated rock above the repository, pen-engineered systems over the 10000-yr period may not pro ide etration of this water into the engineered barrier system, dis-sufficient assurance about the performance of the site. The solution of radionuclides from the waste, slow downward general guidelines of 10CFR960 incorporate the intent of the transport of the dissolved material to the saturated rock below technical criteria of 10CFR60 relative to siting considerations. the repository, and horizontal transport through saturated For developing a site charactenzation program from the appli- rock to the accessible environment. The elements of the sys- ' cable regulations,10CFR960 expands on the 10CFR60 re- tem that can be expected to act as barriers to this sequence are quirements. the unsaturated rock units above and be!ow the repository, the The process of deriving a site characterization program saturated rock, and the engineered barrier system. For rneet-from the applicable regulations was approached by the DOE ing the release standard, the DOE chose to rely on all of these through the use of two basic organizing principles. One orga- system elements. nizing principle is a hierarchical structure of questions about Realizing that each element might have several features regulatory criteria related to the acquisition of site data. This that could contribute to waste isolation, the DOE next chose set of questions is called an issues hierarchy, and it provides the features to be relied on. According to the available evi-a topical organizing framework for developing a site charac- dence, the water moves so slowly that it would not be ex-terizauon program. pected to travel through the units below the repository in the The second basic organizing principle used by the DOE 10000 yr governed by the release stande1, whether it carried and its contractors to develop a site characterization program radionuclides or not. Because the wates a generally confined is called performance allocation. For each issue in the issues to the rock matrix,it would not be expected to flow signifi-hierarch), a resolution strategy is developed. These strategies cantly in fractures or to cross the air sap that eists in the involve the identification of elements of the disposal system engineered barrier system between the rock and th: wastet the that are relevant to isolation and containment of waste or to water would therefore not be expected to reach the waste. Fur-radiological safsty. It is then possible to identify performance thermore, preliminary studies have suggested that the quan. measures and information needed from the site characteriza- tity of moving water is so small that it mas not be able to tion program. This information, coupled with information significantly corrode the waste containers ar.d dissolve radio-about confidence in existing data and the confidene required nuclides, even if water could cross the air gap. Some final sig-in the data to be obtained, allows the development of tesang nificant features of the unsaturated rock and water are their strategies for field programs, geochemical properties, w hich would tend to limit radionuclide dissolution and to retard radionuclide transport. The DOE felt it pruuent to rely on all four of these features: si w watu m went, unau amounts of watu, connnement 4- A "top Level" Strate 9Y for Postclosure of water to the rock matrix, and radionuclide retardacon. Perforrnance Assessment of Yucca Mountain, Choosing all four features is a way of dealing with uncer-Felfon W. Bingham (SNL) tainty. If future evidence shows, for exaraple, that the water movement is faster than the current evidence suggests, the in denning the studies needed for characterizing the Yucca DOE may need to use the other features for demonstrating Mountain site, the U.S. Department of Energy (DOE) began compliance, from the following principle: The data that must be collected Reasoning similarly, the DOE elected to include two other are the data that the DOE expects to use in demonstrating potentially useful repository system elements in the strategy: compliance with the regulations governing a repository. An the saturated rock units, which add to the groundwater travei early step in denning the studies was therefore the formula- time, and the engineered-banier system, which will control the tion of a strategy for demonstrating this corneliance; from rate at which radionuclides can be released to the unsaturated that strategy the DOE has denved lists of needed data and rock units. The DOE elected to use these two system elements plans to prodde those data. The compkte strategy that the as "backup" barriers, meaning that it does not expect to rely DOR formulated is complet enough to fi'd bundreds of pages primanly on them unless future data show the unsaturated in - : ca Mountain site-characterization plan. At its high- rock to be inadequate for meeting the re! case standard. Includ-ew, least detailed level, howeser, the strategy rests simply on ing these barriers is another way of dealing with uncertainty;
. 1 l
1 216 Tuff Characterization Activities-li their role will be to add confidence, if necessary, that the structure and serves a function in an unsaturated site by repository system will be able to perform at a level beyond ichibiting contact of water with the container, that provided by the primary barriers. He waste package is being designed to be compatible with The next step in developing the top-level strategy was to t.nd take advantage of the unsaturated zone environment. An construct quantitative expressions that further explain @ d- additional design feature of the EBS is engineering the ther-ance the DOE expects to place on each element and feature, mal field in the repository to keep a substantial number of For guiding the sites:haracterization work, such statements are waste packages above the local boiling point of water (97'C) more useful than qualitative statements, because they convey for hundreds of years. This will enhance the already dry con-to the planners of tests some essentialinformation about what ditions expected in the repos9ery, the tests need to accomplish. The DOE made these quantita. The container is based on a corrosion resistance (as . opposed to corrosion allowance) concept. Approximately 3 m tive statements in terms of the numerical values that the selected site features are conservatively expected to have. The long,0.7 m in diameter, and I cm thick,it will be fabricated quantitative statements are in no sense criteria that the DOE from metallic materials currently under consideration (aus. fe<s the Yucca Mountain site must meet. They are simply tenitic or copper alloys) or redesigned from a hst of alternate g.es for planning site characterization-guides, based on materials and concepts. A detailed process of establishing cunent understuding, that will be changed if future measure- selection criteria and making the selection will be reviewed mentMow the current understanding to be incorrect. thoroughly. Both testing and modeling are being utilized to ExteWons of this top-level strategy to levels of much select the appropriate material and predict performance over greater detail are necessary for a number of reasons; for exam- the very long time periods. The waste forms will be both borosilicate glass in stainless - plc, the need to consider unlikely future events and processes requires strategies for dealing with them. The DOE has, of steel pour canisters and spent fuel. The glass waste sources are course, also developed detalled strategies for showing compli- the defense waste processing facility at Savannah River and ance with man) other regulations in addition to the release the demonstration project at the West Valley, New York, site, standard. The site-characterization plan contains full explana- The spent fuel will consist of both pressurized and boiling tions of all these strategies. water reactor fuel from U.S. commercial reactors. It may be disposed of as either intact assemblies or consolidated fuel reds. Although a variety of design concepts exist to accommo-date thnari us waste f nns, the basic c nfiguration of waste
- 5. Assessment of an Engineered Barrier Sys. form, container, air gap, and hner is common for all, tem and Design of W3ste Packages, L. Ram
- Assessment of performance of the waste package and EBS spott (LLNL) is based on a!!ocating performance for various waste package components toward overall design objectives. Then, computer The U.S. Nuclear Regulatwy Commission regulation modeling will be used in conjunction with testing to assess 10CFr.60 establishes two major performance objectives for the whether the allocations are met or exceeded. Because of the engineered barrier system (EBS): substandally complete con- unprecedented time period considered, computer modeling is tainment within the waste packages for up to 1000 yr and ccr.. essential. A significant issue will be. validation of the computer trolof the release rate from the EBS for 10000 yr. The EBS models.
is defined in 10CFR60 as the waste packages and the under. ground structure, not including shafts and boreholes. The U.S. Department of Energy has adopted a tenrative interpre- 6. Preliminary Estimates of Groundwater tation of the EBS boundary as the cdge of the emplacement Travel T.ime at Yucca Mounta.in, Scott Sm. nock, hole;i.e., the EBS consists of anything inside the emplacement hole. Such a boundary is comervative and simple to define. Tom Lin (SNL) Because the contaMment performance objectie, e in 10CFR60 is qualitative, the DOE has tentatively interpreted "substan- This paper presents the assumptions, methods, and results tielly complete containm:nt"in terms of quantitative design of a probabilistic approach to the calculation of groundwater objectives. Briefly summarized, these design objectives are as travel times to the water table below Yucca Mountain, follows: Nevada. More detailed infonnation is available in Ref.1. Data t supp rt the aralyses were abstracted from formal and
- 1. Eighty percent of the waste packages will retain all of "I ""*I E ".s generated by the start of several organira-their radioactivity for 1000 yr after permanent closure of the tions participaung m the Nevada Nuclear Waste Storage in-repository. vestigations (NNWSI) project activities, namely, the U.S.
- 2. At any time during the 1000-yr containment period, at Geological Survey, Los Alamos National Laboratory, Law-least 99% of the radioactivity inventory at that time will be rence Livermore National Laboratories, and Sandia National retained within the set of waste packages. Laboratories (SNL).
! Because Dow in the portion of the unsrurated zone below i
- 3. Any releases that do occur should he gradual such that the proposed repository is probably nearly steady state and rMease from the EBS in any year should not exceed one part vertical, the hydraulic gradient was assumed to equal mines in 100000 of the radioactivity inventory present in that year. one (-1)in our model. This means that the flow was assumed The controlled release performance objective in 10CFR60 to be driven vertically downward solely by elevation head reauires that the yearly radionuclide release rate from EBS fol- along the directin of gravity. On the basis of this assumption, low ng the containment period and extending until 10000 yr i a reasonable ap. .oximation of the velocity of water through after s osure shall net cred one part in 100N)0 of the inven- the unsaturated zone was obtained by dividing the flux by an tory of ea6 tuclide calculated 'o be preserv. at 1000 yr after effectne porosity. Flux was assigned as a boundary condition.
Effective porosides and saturated hydraulic conductivities were closure. The curreat conceptual des:gn for tra EBS, which includes derived from experimental measurements. Travel time was the waste package, consists of the waste form, a contamer, an determined simply by dividing the distance of flow by the air gap, and a borehole liner. The borehole liner is included velocity. Tlvs was done for each of several stacked calcula-t to ensure retrievability of the waste for at least 50 yr, as tional elements within each hydrogeologic unit for each of 963 required in 10CFR60.111. The air gap is pan of the engineered vertical columns (Fig.1). L
Tuff Characterization Activities-li 217 A . r
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After a boundary value of flux was assigned, a value of The results provided some of the information used to sup-porosity and saturated hydraulic conductivity was randomly port the NNWS! environmental assessment2 and the site char-sampled for each calculational element from a distnbution of acterization plan3 and indicate that for the upper limit of values associated with the matrix material of each hydrogec- percolation flux below the repository level at Yucca Mountain logic unit. If the assigned flux exceeded the sampled saturated (0.5 mm/yr), groundwater travel times have a mean of hydraulic conductivity for an element Dow velocity was as. ~43 000 yr and a standard deviation of -12000 yr; <!'i of sumed to equal tin excess aux divided b) a fixed fracture the calculated travei times are <10000 yr. Therefore, the pres-porosity; otherwise, the flo u velocity was set equal to the flux ent modelindicates that the Yucca Mountain repository site divided by the sampled ms trix porosity, corrected for satura- would comply with regulatory requirements, tion to yield an effective pt tosity. Travel times for all elements The foDowing conclusions drawn from the work, however, in a column were added to produce a total for each column. suggest further refinement of models and augmentation of The sampling process was repeated in a Monte Carlo fashion data that can reduce remaining uncertainties: to produce a set of travel times for each column with an asso-ciated expected value (mean) and standard deviation. Results 1. If the percolating flux is less than average saturated from the analyses were compiled in the forms of histograms, matrix hydraulic conductivity and if matrix suction can draw cumulative distnbutions, and isochron maps of groundwater water from fractures at the same rate as it moves within matrix travel time from the disturbed zone to the water table (Fig. 2). blocks, then groundwater travel times from the isturbed zone s- _
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0 20 40 60 80 segg GROUNDWATER TRAVEL TIME (108 yr) (a) (b) Fig. 2. (a) Cumulative distribution and histograin of travel times for all columns and all Monte Carlo iterations and (b) isochron map of expected (mean) travel times for upper bound flux of 0.5 mm/yr, to the water table will exceed 1000 yr with a very high level of classical mass-balance, boundary-value flow equations, which probability and are likely to exceed 10000 yr as well, also with are highly nonlinear in unsaturated materials, and (c) provide a high level of probability. Experimental and field data on the estimates of the distribution of travel times along all potential relations between matrix and fracture flow at Yucca Mountain flow paths through the geometrically variable unsaturated will be paramount in determining whethe. our current concep- zone. Future work will focus on developing a suite of single-tual assumptions and derived travel times are correct. and multiple-dimension numerical models that incorporate alternative conceptual models (e.g., unit gradient or continu-
- 2. ne travel-time distribution appears most sensitive to ous calculated pressure field). Results of calculations based on flux, correlation lengths, and spatial variations of saturated this suite of models will be interpreted to provide bounds on, matrix hydraulic conductivity. Less sensitivity is attributed to and best estimites of, the potential groundwater travel-time effective porosity, in most cases, hydrogeologie data are distribution at Yucca Mountain.
insurficient for performing geostatistical analyses. Collection of sufficient measurements to support good estimates of 1. Y. T. LIN M. S. TIERNEY. "Preliminary Estimates of means, standard deviations, and spatia) cross correlations of Groundwater Travel Time and Radionuclide Transport at all hydrogeologic parameters along the flow paths below the the Yucca Mountain Regitory Site," SAND 85 2701, S. proposed repository is strongly recommended. Site-character. SINNOCK. Ed., Sandia National Labs. (1986h ization studies should provide sufficient hydrogeologic data 2. "Environmental Assessment: Yucca Mountain Site, Nevada for modeling the groundwater travel time based on reliable Research and Development Area, Nevada " DOE /RW-statistical treatment of site properties. 0073, U.S. Department of Energy, Office of Civilian Ra.
- 3. ne potential for lateral flow and concentration of flux dioactive Waste Management (1986).
along fault zones or other conduits needs to be investigated
- 3. "Site Characterization Plan: Yucca Mountain Site, Nevada before the distribution of travel times can be confidently inter- Research and Developrnent Area, Nevada: Consultation preted as representing the fastest paths of likely radionuclide Draft," U.S. Department of Energy, Office of Civilian travel. Further refinements of the present model will be nec- Radioactive Waste.
essary to account for such potential flux variations in space and will be developed as better conceptual understanding of flow in unsaturated, fractured porous tuff and additional data are acquired for the Yucca Mountain site. 7. Assessment of Radionuclide Retardation, Current work in SNL's modeling task is addressing the R. J. Herbst,1. A. Canepa (LANL) effects of assumptions about the unit hydraulic gradient and vertical one<fitnensionality on the potential travel-time distri- Radionucbde migration in the unsaturated and raturated bution. Given the limitations ot' current cornputing facilities, rock zones composing the Yucca Moumairi site may be retarded compared with groundwater movement. Predicting it appurs that trade-offs must be made among desires to (a) the potential for retardation by processes that include sorp-explicit:y account for scale-dependent spatial heterogeneity of material properties and boundary conditions, (b) solve the tion, dispersion, and diffusion require a thorough geologic
l l l Tuff Characterization Activities-ll 219 characterization of this cand;date site for the disposal of radio- repository must ensure that cumulative radionuclide releases a:tive waste, augmented by geochemical laboratory experi. to the accessible environment comply with U c. Environmen-ments and modeling. The retardation phenomenon is complex, tal Protection Agency release limits. Substantially complete requiring knowledge of the following: containment must be provided by the waste packages for 300
- 1. history of past alteration and the current petrologic and t 1000 yr. All of these functions must be maintained should mineralogic characters of How paths to the accessible a severe seismic event occur and must be achieved *ith reason-environment ably availa,ble , technology.
The seismic phenomena of m , ierest for the preclosure
- 2. stsbility of these characters as a function of the condi- period are vibratory ground motion from a nearby earthquake doa expected after waste emplacement,i.e., a concep- or unoerground nuclear explosion (UNE), faulting beneath tual model of mineral evolution surface facilities that are important to safety, and faulting in underground areas of emplaced waste. For the postelosure
- 3. current composition of the ambient groundwater and probable changes in this composition as a result of period, carthquake ground motion, underground faultmg, and seismically mduced adverse changes m hydrologic condite expected changes in mineralogy and hydrology, i.e., a have oeen identified as the most important seismic phenom-groundwater chemistry model ena to oc characterized. The Nevada Nuclear %ste Site Inves-
- 4. solubility of radionuclides and their propensity to form tigations project site characterization plan describes a number colloids under the conditions expected to exist along of seismic parameters that are needed for repository design or now paths to the accesshle environment performance assessment, along with tentative goals for each parameter. Key parameters, goals, and arrent assessments, all
- 5. retardation capacity of the natural rock and mineral subject to change as site characterization progresses, are sum-barriers, including a thorotgh understanding of the marized in this paper.
mechanisms of the retardation processes. A comprehensive geochemical / physical modelincorporat- GROUND MOTION iry thi,s information and capable of predicting radionuclide The goal for a design-basis earthquake for facilities impor-nugration rates in three dimensions with known certamty must . tant t safety (FITS) during the preclosure period is a ground-also be developed. This model will enable formulation of a moti n description that envelopes the most probable ground conclusive statement about the role that retardation phenom-ena may play in inhibiting radionuclide migration. m tion from I yr curnulative shp earthquakes on nearby faults. A 10000-yr cumulative shp earthquake is a postulated Fe'rviogic and mineralogic characterizations of rock sam. event that corresponds to a fault displacement, which, occur-pies from the existing drill hole core from Yucca Mountain are ring every 10000 yr, would produce the average slip rate nearing completion. Potentially sorptive minerals in likely flow observed during recent (Quaternary) geologic time. Current paths have been identified. Petrologic and mineralogie verti- informati n suggests that an earthquake of ~6{ magnitude cal profiles are emerging as a result of these efforts. Latera! n the Paintbrusn Canyon fault. -l km from the conceptual vanability and uncertainties in their distribution remain to be site of surface waste-handling facilities, will be the design-basts investigated through additional drilling and the characteriza. seismic event. The most probable peak ground acce!cration for tion of samples from an exploratory shaft scheduled to be such an event appears to be -0.5 gravity. (Engineering mea. constructed. sures to accommodate this level of acceleration in the design Thermodynamic and kinetic data for the sorptive miner-of FITS are readily available.) als present at the Yucca Mountain site are being developed , An ther goal for the design. basis earthquake i,s that its expenmentally. These data are being used to model mineral evolution and forecast stability. Hydrothermal-mineral, nat- annyal. prob,abihty of excecdance shall be on the order of 10 to 10 /yr. Because this range has been found to corre-ural analogues are being studied to support and validate this spond to the power psmicand plants design bases because the noi mineral evolution model. sk profile of aarepository numberisof U.S. nuclear Radionuclide si .ubility, che character of radionuclide solu. tions, and radiocolloid formation and stability are being inves- expected to be lower than that of a nuclear, power plant, this goal appears to be quitt gn dgated. Actinide speciation in dilute solutions is emerging as seismic hazard estimates ,servative. indicate that thePrehmmary pro probabilistic an important area of uncertainty requiring further study. exceeding 0.5 gravity at tiie site is -1 to /yr.5 x 10_,bability of Empirical, static batch, and dynamic column sorption The maximum potential ground motion from a UNE at experiments are used to measure intrinsic sorptive potential and the retardative capacity of largely unaltered rock speci- the , Nevada test site (bTS) is not expected to exceed the design-basis earthquake ground motion. The Buckboard Mesa area, mens. The column experiments can be analyzed to differen- 23 km from the site, is the closest area of potential testing of tiate retardine processes and rnechanisms. high-yield nuclear devices. The onset of damage to high-rise The experimental data and their interpretation are being incorporated into a geochemicaUphysical model, TRACR3D, buildings in Las % egas limits,the yield in this area to 700 kt (Ref. 4). (Current national pobey is to limit test yields to 150 kt 2 three-dimensional, trsnsport code, will be used to assess the or less.) Regression relationships developed from recordings retardadon potendal of mineral assemblages in and under the f nuclear tests at NTS predict a peak acceleration of -0.06 proposed repository horizon in Yucca Mountain. Field tests t 0.24 gravity for a 700-kt shot at a 23.km distany, account. to validate TRACR3D are also planned. ing for local geologic effe' cts on ground motion. These ef-fccts will be investigated in detail during site characterization, and the predicted motions will be reilnw. 8, Assessment of Seismic Hazards at Yucca Mountain, Jerry L. King, Gerald A. Frazier, Terry FAULTING A. Grant (SAIC, Las Vegas) Although the focadations of the surface waste handling buildings could be engineered to withstand substantial surface SEISMIC II AZARD INFORMATION NEEDS faulting, the preferred design solution is to locate these struc-During the preclosure time period (-lCv n), the prospec- tures where the potential for such faulting is very low. One tive geologic repmitory at Yucca Mountain must provide for goal is to identify faults w thin 100 m of prospective sites of public ard worker radiological safety and retrievability of surface FITS that have a probability >10Wyr of slipping emplaced waste. Doring the postelosure period (100X' yr), the $ cm or more; faults meeting this criterion would be avoided.
220 Tuff Characterization Activities-ll Such faults are not currently thought to exist at carididate at the repository. Since the purpose of the accident-conditions sites, but this must be confirmed by trenching surface 1nate- assessment was to support the development of an initial Q list, rials and, where possible, dating continuous geologic honzons, worker doses were not calculated. The normal-conditions A second goalis to conGrm the current assessment that the assessment estimated off-site public doses as well as on-site total annual probability of experiencing >5 cm of fault off- worker doses resulting from the various anticipa&d routine set beneath surface FITS is < 10*/yr. This probability eval- radioactive releases and sources.1 'e purpm / u,e normal-uation will consider, for example, the likelihood of secondary conditions assessmeet was to evaluate the preliminary Yucca faulting at surface FITS sites should an earthquake occur on Mountain repository des'in and identify those operations and the Paintbrush Canyon fault or some other local fault. aspects that are most important to radbtion safety for the For the postclosure period, the goal for site characteriza- repository (e.g., those operations tcat are tbc largest contrib-tion is to demonstrate that the annual probability of faulting utors to the occupational doses of individuas workers). The with displacement >5 cm in areas cf emplaced waste is general approach and some of the results of these safety
<10"/yr. Current information suggests that all goals related assessments are summarized below.
to faulting will be met. The appro,ch taken for the accident- onditions radiolog-ical safety assessment was probabilistiet i.e., the frequency of ccurrence of an accident was considered in deciding whether ADVERSE CHANGES TO IlYDROLOGIC or n t to calculate off site dose consequences for that acci-CONDITIONS dent, and the end results included estimates of accident fre-It is conceivaNe that local earthquake activity could cause quencies. The procedure used in this assessment consisted of increased percolation of water through the unsaturated zone five steps: or could increase the elevation of the water table during the 1. A repository facility and systems model was developed postclosure period. For example, thc average percolation flux for use in the development of initiating events. might be changed by a fault offset that creates surface im-poundments, alters drainage, or, by the juxtaposition of trans. 2. A comprehensive list ofinternal and externalinitiating missive and nontransmissive geologic units, creates perched events was devebped, and some preliminary screening on the water tables. The tentative goal for site characterization is to basis of credibility and applicabilit:' to the site was performed. demonstrate that the probability of increasing the average per- 3. An event tree was developed for each of the initiating colation flux through the repository by a factor of >2 is events that logically and systematically described the various
<10-8/yr. Juxtaposition of geologic units in or near the satu* accident sequences resulting from the occurrence ofin erme-rated zone might affect the water table; the goal is to demon- diate events.
strate with high confidence that this occurrence would not cause the water table to nse to within 100 m of the repository 4. After con pietion of the event trees, a probability assess-horizon in 10000 yr. Strain changes in the rock mass due to ment of the accident sequences was performed, and each faulting might also affect the water-table elevation. The cor. initiating event was assigned a frequency of occurrence and responding goalis to demonstrate that the probability of an eacn intermediate event, a probability of occurrence. At inis ircrea:e in the potentiometric level of the groundwater to point more screening of accidents was performed based on fre-850 m meaa sea level (MSL) due to strain changes is s.10-5/yr. quency, fThelowest elevation of the repository would be above 1000 m 5. The final step of the accident assessment was the cal. NISL.) Current information suggests that all goals re:ated to culation of off-site dose consequences for each remaining acci-seismically mduced hydrologic changes will be met. dent sequence. Dere were 149 accident sequences for which off-site dose
- 1. L. REITER, R. E. JACKSON, "Seismic Hazard Review consequences were calculated. Of these,45 had essentially zero for the Systematic Evaluation Program- A Use of Prob- off-site dose consequences. The remaming 104 accident ability in Decision Making " NUREG-0967, U.S. Nuclear sequences had off-site dose consequences ranging from 0.01 Regulatory Comrmssion (1983). mrem to -2 rem. The frequencies of occurrence associated with these accident sequences ranged from an extremely
- 2. "Technical Basis and Paramern. e Study of Ground Mou.on unlikely 10*/yr to ~10 /yr. 4 Those accidents with off-site and Surface Rupture llazard Evaluations at Yucca Moun* dose consequences approaching 2 rem had low frequencies rain, Nevada," SANDS 6 7013, prepared by URS/ John A. (i.e., below 10-s/yr).
Blume & Associates (1987). De approach taken for the normaleonditions assessment is simple and straightforward. To calculate worker doses, the
- 3. D. M. PERKINS, P. C. THENHAUS, S. L. HANSON, radiation conditions in and around the repository were esti-S. T. ALGERMISSEN, "A Reconnaissance Assessment of mated. These conditions included direct radiation levels, con-Probabilistic Eatthquake Accelerations at the Nevada Test centrati ns and compostuon of gaseous radionuclides, and Site," USGS-OFR-87 '99, U.S. Geological Survey (1987). concentrations and compositions of airborne particulate radio-
- 4. L. J. VORTMAN, "Ground Motion Produced at Yucca nuclides. Direct radiation levels were calculated assuming an Mountain from Pahute Mesa Underground Nuclear Explo. average spent fuel age of 10 yr, a burnup of 27.5 GWd/
sions," SAND 85 1605. Sandia National Labs. (1986). tonne U for boiling water reactor fuel, and a burnup of 33 GWd/ tonne U foi pressurized water reactor fuel. Defense high-level waste was assumed to be 5-yr-old sludge and 15-yr-Id supernate. Airborne radioactivity levels were estimated 9* Assessrnent of Worker and Nonworker using analytical techniques developed under some simplifying Radiological Safety of a Repository, T. W. Laub assumptions. such as the importance of resuspension and hot-(SNL) cell leakage. Off site public doses were composed entirely of immersion and inhalation doses resulting from atrnospheric Preliminary assessments of worker and nonworker radio- transport of anticipated releases of radioactive materials. logical safety for both normal and accident conditions during Whole body and cntical-organ doses from airborne radio-the preclosure period have been performed for the proposed actise materials were found to be at least one order of mag. Yucca Mountain repository. The accident-conditions assess- nitude less than the 1 rem /yr U.S. Department of Energy ment estimated off site doses resulting from credible accidents (DOE) design objective. Worker doses from direct gamma
Tuff Characterization Activities-ll 221 rsdiation were mucu more significant than those from air- members of the public within an 80-km radius of the site was borne radioactivity. As expected, direct radiation doses c'alculated to be 0.012 person-rem for ground.!evel releases. depended strongly on the mode of operation 9ing used by in conclusion, the accident-conditions safety assessment workers (e.g., contact-handling techniques or remote-handling identified several accident sequences that could result in off-icchniques). Estimated direct doses to repository workers did site doses approaching I rem but had associated frequencies not exceed the 10CFR20 regulatory limit of 5 rern/yr but did that w ere below 10'5/yr. Nevertheless, the assessment did iden-exceed the DOE design objective of I rem /yr. Several cask- tify areas of the repository and certain systems and equipment handling tasks that involved worker contact were identified as that may require extra attention in design and/or fabrication major contnbutors to the direct radiation doses to workers. (e.g., enhanced quality assurance). The normal-conditions as. Ground. level releases of radioactise materials re ulted in sessment indicated that public and worker doses due to air-a calculated wbole-body dose of 0.01 mrem /yr and a maxi. borne sources of radianon will be well below 25 mrem /yr for mum critical-organ oose of 0.03 mrem /yr for a maximally the public and
- ell below I rem /yr for the worker. The major exposed off. site mdividual assumed to be at the site boundary, contnbu' ors to worker doses from direct radiation were cask.
$ km from the release point. These doses are weil below the handling operations that invo'ved worker contact, indicating linuts for normal operations of 25 mrem /yr to the whole body thn, in future design phases, remote-handling techniques for or 75 mrem /yr to any critical organ set forth in 40CFR191. these operauons should be investigated for incorporation into The corresponding total population dose (whole body) for the design.
l l t l
, w
i e 238 TECHNOLOGY TRANSFER AND QUALITY ASSURANCE Cosponsored by the isotopes and Radiation and the Fuel Cycle and Waste Management Divisions Session Organizer: D. H. Alexander (DOE) All Papers invited
- 1. Foreign Cooperative Technology Develop. and buffer / container and sealing materials testing. Test plan-ment and Transfer, R. J. Schassburger (DOE, ning for seven underground tests is ongoing.
Argonne), R. A. Robinson (Battelle/OWTD) 2, p ,,,,, ,,,,, ,,,,,, ,,,,S,,gy,,; zg;,g,,y 5,,,,,,, ge sphere modeling, laboratory experiments on nuclide migra. INTRODUCTION tion m fractured rock, and exchange of geohydrologic and sys. It is the policy of the U.S. Department of Energy (DOE) tems performance assessnient codes such as AECL's SYVAC2. that,in pursuing the development of mined geologic repcsi-tories in the United States, the waste isolation program will 3. Field Testing Investigations: The field testing investiga-continue to actively support international cooperation and tions encompass a variety of hydrologic flow studie: that are exchange activities that are judged to be in the best interest of being conducted in the Whiteshell, URL, and Atikokan re-the program and in compliace with the Nuclear Waste Policy gions in Canada. Also, a borehole laboratory is being devel-Act of 1982, SY. 223. oped to provide a controlled test site for groundwater flow. Because there are common technicalissues and because geochemical a id geophysics instrumentation, and measure-technology development often requires large expenditures of rnent technique development. funds and dedication of significant capital resources, it is advantageous to cooperate with foreign organizations carry- 4. Shaft Ertension and Characterization The shaft at the ing out similar activities. The DOE's Office of Civilian Radio- URL is being extended from a depth of 240 to 455 m-typical active Waste Managemcnt is working on cooperative nuclear of geologic repository depth. Geologic characterization of the waste isolation technology development programs with the shaft and excavation response of a major subhorizontal frac-Organization for Economic Cooperetion and Development / ture zone that intersects the shaft are an integral part of the Nuclear Energy Agency (OECD/NEA), Canada's Atomic shaft construction activities. Innovative shaft construction Energy of Canada, Limited (AECL), Sweden Switzerland, techniques (e.g., fuu-face versus benching and bottom cleaning and the Federal Republic of Germany. Bilateral and multina- for mapping) were used and a special five. deck Gauoway stage tional agreements that support information and personnel ex- was designed for shaft drilling and mucking equipment, change are also in place with the International Atomic Energy ground control installation, shaft furnishing installation, map-Agency, Commission of European Communities, Belgium, ping, and instrument array drilling. United Kingdom France, Brazil, and Japan. HYDROCOIN and INTRAVAL are two other multinational projects involv- OECD/NEA STRIPA PROJECT ing groundwater flow benchmarking exercises. Joint cooperative projects between the United States and This paper describes recent technology results that have Sweden were started in 1977, involving field tests in and been obta2ned in DOE's foreign cooperative programs. Spe- around the Swedish Stnpa facility. In 1979 an OECD/NEA c:fic technology development studies are discussed for coop multinational Stripa project was organized by five member crative efforts with Canada. OECD/NEA, and a natural countries with phsse I and !! studies conducted from 1980 to analog project in Braril. 1987, and phase III tasks to be completed from 1936 to 1991. Phase I and Il studies included hydrologicalinvestigations DOE /AECL COOPERATIVE AGREEMENT m boreholes, migration in single fractures, buffer mass tests, In March 1986, the DOE and Canada's AECL entered development of geophysical and hydraulic crosshole tech-into a subsidiary agreement under their bilateral agreement to niques, three. dimensional tracer experiments, borehole and conduct a joint experimental and analgical technology devel- shaft sealing, and fracture flow borehole pumping tests. opment project on the characterization of geologic formations. Phase 111 studies include the following: This cooperative program consists of four major tasks: 1. Eracture flow and Nuclide Migration: Phases I and 11
- l. Cooperative Experimental Program at the Underground studies involved development of tools and methods for the Research Laboratory (URLk This task involves geotechnical geological, hydrogeological, and geochemical charactenzation characterization of the rock mass surrounding underground of fractured rock. Studies of possible mechanisms of nuclide experiments. These experiments include excavation response, transport by groundwater flow in fractures within the rock thermo-hydrologic mechanical response, fracture migration, were also conducted.
n - .
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- Technology Transfer and Quality Assurance 239 In phase !!! the primary emphasis will rely on the appli. fostered by a sense of urgenre in the need to demonstrate a cation of the technology deveieped in phases I and il to char. safe means of disposal of nuclear waste and a consequent actenze a relatively undisturbed rock mass (125 x 125 x 50 m). desire to avoid inefficient duplication of all the necessary Characterization willinclude predicting groundwater flow and research in every nation.
nuclide transport inside the rock mass and subsequently com- In the geosciences area, each country has tendea to focus paring these predictions with data from field measurements. its site characterization research on those potentially suitable r ek types that provid: 2 most flexibilityin siting. An im-
- 2. Groundwater Flow Path Sealing: Again based on infor-portant c nsideration for each national program as the extent mation deve!oped in phases I and II, studies will be performed to which site characterization methods and techruques devel-to identify, select, and evaluate various sea!ag materials that oped r demonstrated in one geologic setting on rock type can possess !cn; term ehemical and mechanical stability. Short- be transferred to others. In addressing this question we will term field tests would then be conducted to obtain in sir; data c nsider three components of site characterization method-on sealing of fractured rock. ology-The Grst component includes what might be called stan-POCOS DE CALDAS dard exploration methods such as geological mapping, remote The multinaticnal Pocos de Caldas naWral analog proj- sensing, airborne and ground geophysical surveys, drilling ect is being undertaken to (a) evaluate the transport and speci- cored boreholes, and borehole geophysical surveys. These are ation of natural radionuclides and rare earth elements in a the methods that are used to establish the geologic framework flow system in crystalline rock under both oxidizing and re- of a site and to initially identify features that might represent ducing conditions, and (b) to evaluate colloid formation and potential pathways for waste migration or that might repre-mobility in natural groundwaters and the role of coiloids in sent potential engineering problems. Although the geopbysi-element transport. cal surveys always need to be calibrated for local areas, all of The initial phase of the projee, has been comoted, with these methods are applicable in principle to site characteriza, the following findings: tion in any rock type or geological setting. For the geophysi-cal smeys in panicular, there are not many case histories
- 1. Natural radionuclide decay profiles around redox fronts documenting the observable characteristics of known and well-preserve a signature of mobilization / transport processes, but understood features of interest m characterizing sites for waste these ax e more complex than was expected and predicted based dsp on a simple dissolution / precipitation model. h second component comprises methods for making
- 2. In regions of water flow through fractures that contain field measurements of important parameters, included would greatly enriched radionuclides and rare earth elements, it is be the instrumentation and procedures for determining or possible to test speciation/ solubility modcIs for safety assess- inferring hydraulic conductivity, hydraulic head, fluid chem-ment. istry, stress, deformation, and physical properties in the im-mediate vicinity of single boreholes, in the rock between
- 3. Methods for characterization of microbial populations borebotes, cr m the rock adjacent to excavations. Virtually all
! and colloids in relevant samples have been devc!oped. research that investigates and documents the operational per- ' formance of such instrumentation and procedures is directly applicab'e to all rock types. This is true for several reasons. I 2. Site Characterization Technology, S. H. In some cases. the measurement is purely physical (such as the distance between fixed anchors). For many important param-l Whitaker(AECL Whiteshell-Canada), A.K. Yonk eters (such as hydrauhc conductivity), the possible range of - (Battelle/OWTD) vacs and the range of values of interest are roughly the same regardless of rock types. Furthermore, for many methods i Site characterization is the process of field and laboratory en ce very cw case es menting instrument per-investigation by which a knowledge and understanding are fumance w eva adng the range of appUcaM. ty o obtained of the geological sating; the potential paths of fluid men m me as ns es 6 a Wwn emf nmmthew instr + flow and waste migration through the rock; the mechanisms ' ' * " " * "" " of thermal, mechamcal, and hydrological response of the rock e tW compeent cesists of metM (m mMcW. mass that might either affect the construction and operation processes of importance using data from the field investiga-of the repository or alter the potential paths of fluid flow an"4 tions. Examples would be methods of modeling fluid flow or waste migration; and the mechanisms of waste migration and rock deformation. Many codes can be applied to a variety of retention along the potential paths. . rock types, but the primary value of research in one rock type The purpose of characterization is to provide the geotech- to site characterization programs in another rock type is in the nicalinformation needed to documentation of case histories where the performance of the
- 1. develop the engineering design of a repository that will code can be compared to a known result and where ambigu-provide a safe environment during disposal opstions ity in the system or situation being modeled is limited.
and after closure The IJ.S. Department of Energy and Atomic Energy of Canada, Limited have established a ecor;erative program to
- 2. predict hydrogeological,7omechanical, and other envi- '. valuate field investigation and mdeling methodologies for ronmental responses at the site to construction, oper- ute characterization. A major component of the cooperative ation, and closure program is a borehole laboratory located -100 km east of
- 3. monitor actual hydrogeological, geomechanical, and Winnipeg, Manitoba, Canada on the Lac du Bonnet batholith, other environmental responses at the site to construe- a granitic intrusive of Archean age bounded by greenstones tion, operation and closure and tonalitic gneisses. The objectives of the borehole labora-
- 4. assess the long-term safety performance of the repos-
"Y""
itory following closure in comparison to regulatory
!. development and testing of methods to investigate the safety criterta. geological, geophysical, geochemical, and hydrological Nuclear waste management research and development has properties of the rock mass at the borehole laboratory benefited since its inception from a high degree of interna- site from the surface, in individual boreholes, and in tionalinformation exchange and cooperation. This has been multiple boreholes
, u
240 Technology Transfer and Quality Assurance
- 2. demonstration of range, accuracy, and resolution of in fractured media using surface and downhole techniques is different methods by comparison against an established critical to our ability to predict performance using models.
and comprehensive data base . These three efforts will address the sbility to gather the necessary data n a eld pr gram to evaluate fractured media,
- 3. cortclation of data from different methods where appro-the applicability of discrete fracture now models to site inves-priate and development of an integrated model of the groundwater and solute transport properties of the 8' .ns and predictions, and the scale effects that may result borehole laboratory ite in ta g la orat ry res ts ,and, applying them to site inves-tigations. All of these invesugauons are ongoms and in vari-
- 4. assessment and development of various analytical and ous stages of completion. It is anticipated that the laboratory numerical modeling capabilities, experiments will be finished within the year and that the field work and model development will lar. for several years.
- 3. Field Studies, Laboratory Experiments, and Modeling investigations in Fractured Media, 4, Instrumentation Developrnent, William F.
Michael A. Deyling (Batfelle/O WTD), Edward S. Ubbes(Battelle/O WDT), Jesse L. Yow, Jr. (LLNI.) Patera (DOE, Argonne) Instrumentation is developed for the Civilian Radioactive Groundwater flow and radionucliae migration are two Waste Managernent Program to n'cet several different (and critical factors in determining the performance of a high. level sometimas conflicting) objecuves. This paper addresses instru-nuclear waste (HLW) repository. Flow and transport in frac- mentation deve;opment for data needs that are related either tured media is a complex problem that must be addressed by directly or indirectly to a repository site, but does not touch both the site characterization programs and predictive mod- on instrumentation for work with waste forms or other mate. el . The Repository Technology Program is investigating thre rials. Consequently, this implies a relatively large scale for the aspects of the problem in cooperative efforts with Canada and measurements, and an in suu setting for instrument perfor-Sweden as weu as in international programs such as INTRA- mance. In this context, instruments are needed for site char-VAL. The methodologies and techniques developed in these acterization to define phenomena, develop models, and obtain programs can be applied to any site investigation that must parameter values, and for later design and performance con-consider fracture flow and transport of radionuclides alog firmation testing in the constructed repository. The former set discrete fractures. of applications is more immediate, and is driven by the needs Laboratory experiments are being performed in coopera- of program design and performance assessroent activities. tion with Atomic Energy of Canada, Limited (AECL) on a A host of general technical and nontechnical issues have large block of granite (~l ra square) with a discrete fracture arisen to chauenge instrumentation development, instruments to investigate dispersion and dUfusion along the fracture. can be classed into geomechanical, geohydrologic, or other Nonreactive and reactive tracers are used in the experiments. specally categories, but these issues cut across artificial clas. Tracers that include uranine, iodine, and cesium are injected sifications. These issues are outlined as follows: under controlled gradients and sampled uniformly along the 1. identification of data needs by measurable parameter fracture discharge surface. Results of the nontesetive tracer experiments will be used to calibrate a radionuclide transport 2. environmental conditions: heat, moisture, chemistry, code (FRACFLO) recently developed at Battelle's Office of and radiation Waste Technology Development. The calibrated models will 3. requirements for remote (noninvasive) measurements then be used to predict the results of experiments that use reac-tise tracers. The experiment and associated medeling are being 4. service life of instrument components and systems considered for use as a test case in the INTRAVAL program.
- 5. redundancy of transducers and instrument systems Development of fracture media groundwater flow codes is ongoing under subcontracts to U.S. Depanment of Energy / 6. redundancy provided by different measurement ap-Repository Technology Program and Battelle with funding proaches from the HLW Repository Program. This developmental
- 7. data transmittal and recording work is aimed at predicting flow through discrete fractures and deactmining the appucability of this approach versus con- 8. calibration of components and systems tinuum models on a site-sized area. Phase ill of the Stripa
- 9. instrument accessibility, repair, and replacement Project will include an exercise to apply the codes DISCEL ,
and JINX at an underground facility where data can be 10. power supplies
- gathered under controlled conditions at a specific location. 11. limited resources (time and money) for development, The codes being developed generate a synthetic fracture net-fabrication, and testing work hsed on fracture statistics gathered from the site being ,
investigated. In theory, the flow calculations using this sim- 12. quality assurance and data validation ,
,ulated frxture network should be representative of conditions 13. pro rietary matters and the roles of the U.S. Depart-at the site. Predictions of the flow system will be made at the ment of Energy, contractors, and manufacturers.
test location and ccmpared with actual conditions found at the site. This test case will be the initial step in validating the frac- Devite this imposing list of issues, several case histories ture flow codes, can be cited to evaluate progress in the area. These include the , A field program near the Underground Research Labora- design of a prototype borehole fracture monitor system for the i tory (URL) in Manitoba, Canada, is under way to investigate Repository Technology Program (RTP), instrument develop- i! the application of single-hole, hydraulic testing in fractured ment and evaluation activities for the Nevada Nuclear Watte 8 media. Two separate boreholes, WRA 2 and WRA-4, drilled Storage Investigation (NNWSI) Spent-Fuel Test -Cumax, and 2 into the Lac Du Bonnet batholith to depths of 830 and 400 m, field trials of high. frequency electromagnetic geotomagraphy re:pectively, are being used to test the appropriateness and for NNWS! hydrologic applications and for RTP grout inva. ! reproducibility of hydraulie tests in zones isolated by inflat- sion studies. 7 able packers. The ability to define the hydrologic flow system A number of other possible sources for useful precedents ! l
l l 1 1 Technology Transfer and Quality Assurance 241 l or solutions exist in ac'dition to the work represented by the associated brine reservoirs, and (c) better definition of the case histories above. The first, obvious choice is commercially hydrologic regime for the WIPP site. The promulgation in available instruments that have been applied in civil works or September 1985, of the EPA standard for geologic reposito. the mineral industries. Somewhat more exotic techniques have rics served to focus the site investigations more directly toward been used in aerospace industries, but their application to addressing those criteria. More than 90 boreholes have been earth materials and processes is not necessanly straightfor- drilled to obtain geologic and/or hydrologic information per. ward. While the advantages of off-the-shelf technology can be taining to the WIPP site. The total costs for the geotechnical negated by special requirements or environmental conditions, site characterization programs through September 1938, will customized solutions to mstrumentation and data acquisition be 545.5M. Program costs were mmimized by pursuing studies problems can be developed with the help of expertise provided in a sequeetial manner, allowing earlier studies to indicate the by commercial organizations if the proprietary aspects of tech- needed investigations and the preferred exploratory program nology trarsfer can be addressed, to address the issue. The site characterization studies regarding these issues have shown that dissolution processes, either regional or local O. History of WIPP Site Characterization and do not threaten the integrity of the WIPP site. Karst hydro $ Lessons Learned, Wendell D. Weart (SNL) geology does not exist at the WIPP site proper, nor will such features impact breach / transport scenarios for WIPP. New The Waste isolation Pilot Plant (WIPP) has been autho. geophysical methods, primanly electromagnetic, have been rized by the U.S. Congress as a research and development applied to assess the potential for brine pockets at a depth of facility to demonstrate the safe disposal of radioactive wastes some 300 m ociv- the WIPP excavations. These surveys indi-generated by defense program activities. After a 5-yr demon. cate that such brine pockets may exist under a portion of the stration phase and on determination of compliance with the site. This potential cannot be confirmed without an extensive Environmental Protection Agency (EPA) standard for geo. drilling program, but since performance assessment modeling logic repositories, the WIPP facility will become a permanent assumes the presence of such brine occurrences, confirmation repository for disposal of defense transuranic wastes. This of their presence is not required. Experimental studies and paper discusses the most significant aspects of the WIPP site modeling of salt deformation indicate future deformation at characterization and some of the lessons learned in the course the WIPP site will not be a factor within the required isola. of these studies. tion time. The hydrologic testing and modeling has established The WIPP site selection began in 1972 with a U.S. Geo. that the Culebra Dolomite, the water-bearing unit of greatest logical Surwy reWew of salt deposits in the United States and interest above the salt, possesses both matrix and fracture a resultant recommendation that a location in the northern porosity. Nonsorbing tracer tests establish that both matrix portion of the Delaware Basin in southeastern New Mexico porosity and fractures are important in the transport process was most likely to prove acceptable. This initial site was at the local scale. Large-scale pumping tests, which create pres-explored by three deep exploratory core holes in 1974 and sure head responses over distances of many thcusand feet, 1975. Evaluauon of the information obtained from these holes have provided good average values of transmissivity over the resulted in a decision to abandon that specine location, due entire WIPP site. State.of.the-art modeling of the hydrologic to the extreme structural deformation of the salt beds at the system can now be accomplished with good confidence. Severallines of esidence, including isotope studies, indicate the horizon of interest. By late 1975, the search for a new site location in the Dela. hydrologic system at WIPP is not at steady state, but is in a ware Basin sait had narrowed to two locations. The present transient phsse following an earlier pluvial period. The site, WIPP site was selected because it had less potential conflict after 13 yr ofinvestigation, is still considered to be an accept. with hydrocarbon resources and the desired salt beds were at able, desirable location for the WIPP. a somewhat shallower, more desirable depth than at the alter. The WIPP site characterization experience has shown that nate site. Selection of this site location without conducting not all the important issues and required tests can be antici. extensive gecphysical surveys and exploratory drilling was pos. pated at the outset. Any exploratory program should have the sible only because tnere was a vast amount of geologic infor. flexibility to add or delete investigations as the site character. l mauon in existence from exploratory work by the petroleum ization proceeds. We have also learned that careful under. l and potash industries, which was available far private exami. ground geologic mapping in shafts and drifts is almost certam nation. This information was adequate to establish that the to reveal details not observable in core. This proved to be an geolog": stratigraphy and structure around the site area were important aspect of selecting the facility horizon and in the acceptable. An exploratory core haie, ERDA9,in the center interpretation of apparent geologic structure as actually being of the proposed site was begun in December 1975. depositional in origin. Geologic and hydrologic studies of the WIPP site have continued until the present time and the site characterization phase will be completed in 1988. An important decision in this 6. DOE Policy: Waste Management QA, Jer-process of site evaluation was that underground validation of Ome SalfZman, uerriff s. Langsfon coor; the geology was accessary, and in 1981 shafts were excavated to allow direct exammation of the salt beds. Exploratory This oaper discusses the policies of the U.S. Department drifts, rather than horizontal core holes, w ere deemed desirable of Energy's (DOE's) Office of Civilian Radioactive Waste and they were mined to the furthest extent of the proposed Management (OCRWM) relative to quality assurance (QA), storage areas. By March 1983, the site had been sufficiently the role of QA within the context of an overall program man-l examined by both surface and subsurface studies to declare it agement system, and the irrportance of adequate and effee. l "vahdated" with respect to the siting guidelines. The siting tive QA prograrns to the succes* and credibility of the civilian guidelines were very similar to those later adopted by the U.S. radioactive waste management program. It notes some of the Department of Energy for selection of sites for cmlian waste key actions being taken to implement OCRWM QA policies repositories. Subsequent to site validation, full facility con. in accordance with the concepts outlined in the OCRWM director's statement of July 13, 1987. struction was authorized. Since 1933, the site characterization studies have focused One of the primary lessons that OCRWM has learned on the three most contentious geotechnicalissues ansing dur. from s3ccessfully managed nuclear utility construction proi-ing the course of the site characterii. 3n. These are (a) salt ects is the essentiality of top-down management attention and dissolution mechanisms and rates, h alt deformat on and comrnitment to the assurance of quality achievement in the ( I _
242 Technology Transfer and Quality Assurance sultation with the NRC to identify and resolve key QA issues. accomplishment of mission objectives under the Nuclear Waste Policy Act. He OCRWM has recognized that,in addi- OCRWM has provided QA program visibility to the NRC by tion to establishing adequate and effecthe QA programs that invitir.g the NRC staff to review and comment on QA plans, and to observe and comment on QA audits of project and are technically oriented, attention must be given to the bro der contractor ectivities, aspect of assuring quality in every activity of the program that significantly affects cost, schedule, performance, and institu-tional relationships. Thus, QA is an integral part of an over- 7, NFiC Overview: ficpository QA, James E. , au OCRWM program management sy* tem that is managed s for quality. Kennedy (NRC) i The OCRWM QA policy requires the establishment and I The U.S. Department of Energy (DOE)is on the thresh-implementation of formel, documented, and auditable QA old of an extensive program for characterizing Yucca Moun- . programs within headquarters, projects, and contractors orga- j nizadons to cover technicalitems and activities that are impor- tain in Nevada to determine if it is a suitable site for the tar.t not only to public and occupational radiological health permanent disposal of high-level nuclear waste. Earlier this . and safety and waste isolation, but are also of special pro- year, the DOE published the Consultation Draft Site Charac-terizadon Plan for the Nevada site, which describes in some ! grammade significance. Tbe OCRWM QA po!"y differendates detail the studies that need to be performed to determine if the , between safety and nonsafety functions by the categorization of technicalitems and acdvides whin a threequality level sys- site is acceptable. In the near future, the final site character-tem. The designadon of quality levels is primarily the respon- izadon plan (SCP) is expected to be issued and large-scale site characterizadon activities to begin. The data and analyses that sibility of a techrdcal manager, who is usually assisted by a will result from the execudon of that plan are expected to be kr.owledgeable QA manager, as is the selection of appropri-the primary basis for the license application to the U.S. Nu- t ate QA program requirements within each quality level, which I is referred to as the graded QA approach. Verificadon that the clear Regulatory Commission (NRC). selected requirements have been implemented effectively is per-Because of the importance of these data and analyses in l formed routinely by line managers and independently by QA the assessment of the suitability of the site and in the demon-stration of that suitability in the NRC licensing process, the ) rnanagers. f Under the OCRWM quality level system, quality level 1 NRC requires in 10CFR60 that site characterization be per-formed under a quality assurance (QA) program. The QA } (QL!)is reserved for technicalitems and activmes that are program is designcd to provide confidence that data are valid, j important to pubth radiological health and safety and waste i retrievable, and reproducible. The documentation produced by isolation, and are subject to compliance with applicabia U.S. Nuclear Regulatory Commission (NRC) ngulations; QL1- the program will form an important part of the record on [ which the suitability of the site is judged in licensing. In addi. , desirnated items are Q-listed. Quality level 2 (QL2) is for the i tion, because the NRC staff can review only a selected pordon assignment of those technical items and acdvides that are not of the data couected, the staff will need to rely on the system ! assigned QLI, but are relat~1 to public and occupadonal radio- ' of controls in the DOE QA program to make findings on the logical health and safety and uaste isolation; QL2-designated acuvides .ad items may support licensing, but are not required overall repository program. Inadequate implementation of QA programs was in part to comply with NRC regulations and are not Q-listed. Quai. responsible for long delays and large cost increases for a num-ity level 3 (QL3) is for the assignment of selected technical ber of nuclear power reactors in the late 1970s and early 1980s. items and activities that are neither important or related to Several plants were canceUed after being nearly completed. radio!ogical or occupational health and safety and waste iso-ladon, but are of such special programmatic significance as to De staff objectives in its QA review of the repcsitory pro-be controlled according to good technical management, work gram are to prevent such an occurrence from happening again by learning from the mistakes of the past and to develop con-practices, and QA requirements within the scope of a formal, documented, and auditable QA program. fidence in the program's adequacy before extensive character-It is important to note that fa!!ure, omission, or degra- ization activities are begun. The staff has a number of activities under way in QA. dation of a QL2-designated technical item or activity could First, the QA regulations imposed on the repository program challenge but not adversely affect the safety function of a are those from the nucicar power reactor program, appropri-QLI-designated item at the time the item is needed to prevent ately modified to takc into account the differences between the or mitigate an accident or isolate waste. It is important to hardware-oriented activides associated with designing and con. l note, also, that NRC design and QA regulations are being structing a nuclear powei plant ana the research and develop-extensively used in developing and implementing the overall ment activides of site characterization. The staff has developed waste management program objectives. o The OCRWM is aware of the potential problems both in guidance that explains what it believes are the appropriate dif-perception and in fact t sat could arise if it became necessary ferences. The guidance is contained in the QA Review Plan f and Generic Technical Positions on Peer Review, Qualifica- ! to change a QL2-designated item to QL1 because of its impor-tion of Existing Data, and the Q-List (i.e. the items and activ-tance to public radiological health and safety or waste isola- ities that are to be covered by the QA program). The staff is g tion. The OCRWM plans to avoid th difficulties experienced g also actively supporting the American Society of Mechanical
,by the nuclear utihties as described in the Ford study by Engineers (ASME) efforts in developing a consensus standard proper management attendon and commitment to the assur- {
(NQA-3) for waste management programs. The staff is a g ance of quality achievement and by demonstrating the ade. member of their waste management subcommittee and is g quacy of achieved quahty, r To strengthen the implementation of OCRWM QA policy, reviewing and commenting on drafts of NQA-3 to ensure OCRWM is amending its QA program description and re. it appropriately implements NRC regulations and can be endorsed by NRC after completion. o quirements documents, to amplify the concepts outlined in the director's QA statement with respect to quality levels, infor-Second, the staff has aMo reviewed and commented on a [ number of DOE documents designed to meet the QA program f macon feedback, vc-ificadon, and overview. The OCFWM is also strengthening its QA organizadonal structure to provide requirements. These include the sections of the SCP address- ( g ing QA; the QA plans and procedures for DOE headquarters. for improved QA program direction, management control, the Nevada project office, and various contractors; and tech- ? and top-down overview, Finally, OCRWM is actively engaged in prelicensing con- nical documents that contain QA information. f. s
Technology Transfer and Quality Assurance 243 WASTE FORM DESCRIITION l COMPLIANCE l PLAN I N QUALIFICATION REPORT LICENSING PRO DUCTION PRODUCTION 4 DATA BASE RECORDS Fig.1. Waste acceptance process (waste pro fucer). The final major area of staff activity is the review of the implementation of the QA program to determine if the plans cuanty Assurance Proorem Desertption and procedures are in fact being followed by the line staff within the program, in the power reactor program, this has sign. Level Waste Form Production been the area *e & most QA problems occurred. Conse-quently, special attention is being given by the staff to this \ ,,,,,. ,,,,, area. The staff condeed its first team .udit of the repository p,,que., p,,que., program in June 1987 at Los ALmos National Laboratory. A ouenty ouesity heavy emphasis was placed on the effectiveness of the program Assurance assurance a as meanred by the quality of technical work,in addition to
,,y,j[,t on o se fpt on assessing the completeness of the documentation. The staff has also conducted a number of observation audits of DOE audits of their contractors.
The DOE is continuing to put into place the necessary QA programs for future site characterization activities. More team audits and observation audits are planned and will become the implementine imp 3*mentine focus of the staff activities as guidance and document reviews Procedures Procedures are completed. Fig. 2, Composite QA program description for a typical HLW fonn production actMty.
- 8. Quality Assurance Requirements for High-Level Waste Form Production, Kenneth A.
Chacey, Charles R. DeLannoy (DOE), Milton H. acceptance process documentation for en uLw producer is Can+oell(Westinghouse Hanford) shown in vig. l. A QA specification has been developed that will be app ed The U.S. Department of Energy (DOE) Defense Waste to those activities important to certification of the product. Management Plan has the objcetive of ihat disposal for high- ne basic requirements are defined in national consensus stan-level waste (HLW) generated from defense programs. The dards and DOE directives. The supplemental require.nents DOE sites that generate HLW are located at the Savannah crable I) identify the QA criteria associated with HLW pro-River Operations Office in Aiken, South Carolina, the Han- duction where additional guidance is needed to facilitate the ford site in Richland, Washington, and the Idaho Operations DOE repository licensing process. Office in Idaho Falls, Idaho. The purpose in the development To ensure that the waste-producer QA programs relating of a quality assurance (QA) specification for organizations to waste acceptance have been prepared in a format that :an involved in HLW production is to establish uniform require- be evaluated by the OCRWM agaimt applicable criteria of the ments that ensure that radioactive waste is converted to a NRC Review Plan for Quality Assurance Programs for High-waste form and canistered in such a way that it is acceptable Level Nuclear Waste Repositories. QA program descriptions in a federal repository licensed by the U.S. Nuclear Regula- will be developed by each waste. form producer.L The QA tory Commission (NRC). programs appued to the waste acceptance process activities To ensure compliance with repository regulatory require- will be evaluated by the OCRWM as the repository license ments, the DOE organization responsible for the license appU. applicant. The program description will coser the basic and cation, the Office of Civilian Radioactive Waste Management supplemental requirements, and will desenbe the role, respon-(OCRWM), establishes the requirements for waste to be ac- sibilities, and interface of the major participants in the waste ceptable for disposal. The mirumum acceptable requirements producer's organization. The individual waste-producer pro-for canistered defense HLW are outlined in waste acceptance grams wdl be tied together by an umbreDa description that will ! specifications (WASs) for each waste-form producer. The be a composite of the major participants (Fig. 2). WASs outline the technical requirements and documentation it is expected that the QA prograrr. descriptions will be to support the acceptability of the product to the OCRWM influential in supporting the acceptability of the product to and the ultimate disposalin a licensed repository. The waste the OCRWM and ultimate disysal of the HLW in a reposi. 1 , _
4 244 Technology Transfer and Quality Assurance
..ctt u weite
- 9. Application of QA to R&D Support of HLW
. Programs, Dennis E. Ryder (PNL)
* *, y cf,*,ct I INTRODUCTION s e cr'a' *e','se'e * 'U'"" ' Quality has always been of primary importance in the se ese se, annese a research and development (R&D) environment. An organiza-tion's ability to attract funds for new or continued research is
=se inmcel ,"l', ,$$', *,",',', largely dependent on the quality of past performance. How-
'""'"1 -
saae ever, with the possible exceptions of peer reviews for fund reeerei seennery allocation and the referee process prii to publication, past
,,c ussese annienu uc quality assurance (QA) activities were primarily informal
- "" "good practices." This resulted in standards of acceptab!c tumn,\
*""h
/ practice that varied from organization to organization.
The increasing complexity of R&D projects and the in-estras tassncnuusenuel creasing need for project results to be upheld outside the seu e.eius essernce treerem entific community (i.e., lawsuits and licensing hearings) are s ucrisu n rer o,e-tens seeincon s.ste sunnere encouraging R&D organizations and their clients to adopt more formalized methods for the scientific process and to ( enny asseresee gone, assureace increase Control over support organizations (i.e., suppliers and Presrom Prestem subcomractors). This has become especially true for R&D-seser un seier e" organizations involved in the high-level waste (HLN) manage-ment programs. One method that is being used is to adapt the sigh teses ente mee-tent ernite form r ei m practices and principles of QA as they are a rre suun armeil" appropriate for R&D activities and objectives.pp
/ Pacific Northwest Laboratory (PNL), operated for the Fig. 3. Typical relationship of QA program descriptions to U.S. Department of Energy (DOE) by Battelle Memorial Insti.
tute, has been involved in HLW projects for a number of support repository licensing, years. The PNL began to implement QA program require-ments within a few HLW repository preliminary studies in 1978. In 1985. PNL developed a comprehensive QA program , TABLE i for R&D activities in support of two of the proposed reposi-9' Supplemental QA Requirements for tory projects. This QA program was developed by the PNL HLW Form Production QA department with a significant amount of support assis-tance and guidance from PNL upper management, the Basalt Title ,_ W ste is,/Jun Project (BWIP), and the Salt Repository Pro-gram Office (SRPO). The QA program has been revised to Controlof EssentialSofruara add a three-level feature and is currently being implemented Peer Review on projects sponsored by the Office of Geologic Repositories Control of Eroenments and Developmental iDOE/OGR), Repository Technology Program (DOE-CH), Nevada Nuclear Waste Storage Investigation (NNWST) Proj-Activities cet, and other HLW projects. Quanticaten of Data Arctwval of Samples DESCRIPTION OF THE ACTUAL WORK ConWf SW Processes Product Certificaten National consensus standard ANSI /ASME NQA 1 (Ref. :) ' was selected by the DOE Office of Civilian Radioactive Waste Readness Renew Management to be the standard on which QA programs for Seiective Ap@ ten of program the repository projects are to be based.5 This standard is r.ot Activities (Ovahty Leveis) directly applicable to the R&D activities performed at PNL. Selecton,Indoctnnat on and Trainsg The PNL, with considerable assistance and guidance from BWIP and SRPO, developed an interpretation of NQA 1 that of Personriel could be applied to the R&D activities. This interpretation is Overview of Quakty Assurance Activdies documented in a Q A manual (PNL-MA-60) and supporting Quanty Records administrauve procedures. , McGeation Control The QA manual and the administrative procedures were Effectiveness Eva'uation developed in early 1985 and implementation was in progress before the end of the year. The primary responsibility for implementing the QA program is delegated to each PNL proj. cet manager. The project manager is orovided with consid-etable assistance from quality engineers that are part of a tory. In this regard, the program descriptions relating to the centralized QA department. This assistance has included train-waste acceptance process activities would bs subject to the concurrence of the OCRWM. To support repository licensing ing, dxurnent review, and suncillance for compliance. A sep-arate section in the QA department has also been perforniag aethities with regard to canistered waste-form production, audits of the individual PNL projects. the program description documents will be prepared by each This paper describes the development process and the cur. waste form producer so that they can be incorporated in the tent structure of the PNL HLW QA program and the orgs-repository license application (Fig. 3). nizational structure used to implement the QA program, and introduces some features that are being added to improve the I, DOE /RW Quality Assurance Requirements for High-Level Waste Form Production, OGR/B 14, U.S. Department of QA program and enhance the understanding and'implemen. tation by the affected PNL staff. One of the improvernents Energy, m_ _ . _ _ , _ _ , _ - _ . .
Technology Transfer and Quality Assurance 245 incluues the establishment vf a three-level system and the gram improvements to make the program c.ssier to understand development and issue of the PNL Good Practices Standard and implement and at the same time assure that all client (GPS). The GPS applies to level 3 Cow risk to PNL, DOE, expectations (i.e., requirements) are complitd with in full. and the public) projects 2nd activities and is in the preliminary process of being implemented at PNL. 1. D. E. RYDER,"Management of QA in an R&D Organi-zation," A Q Quality Congress Transactions, Boston, RESULTS Massachusetts (May 1983). Because of the substantial support of the PSL lir.e and project management, the PNL repository QA program was 2. "Quality Assurance Program Requirements for Nuclear successfully implemented from the start. The various PNL Power Plants," ANSI /ASME NQA.I.1986, American So-projects have been :udited by the clients (including NRC ciety of Mechanical Engineers, New York. observers in several instances) and relatively few and minor findings and observations have been the result. The PNL has 3. "Quality Assurance Management Policies and Require-attempted to learn from the audit results and its own obser- ments," DOE /RW-0032 Office of Civilian Radivactive vations and assessments and is currently workir.g on QA pro- Waste Management U.S. Department of Energy (1985).
LICENSING SUPPORT SYSTEM ADVISORY COMMITTEE PARTICIPANTS MEETING ON RAW DATA JUNE 9,1988 , TIME WHAI WtiO. 9:00-9:05 INTRODUCTIONS AROUND THE ROOM ALL 9:05-9:15 INTRODUCTORY REMARKS DOE /HQ 9:15-9:25 INTRODUCTORY REMARKS STATE OF NEVADA 9:25-9:30 INTRODUCTORY REMARKS \NMPO 9:30-10:45 U.S. GEOLOGICAL SURVEY A. FLINT PRESENTATION 10:45-11:15 SANDIA NATIONAL LABORATORY F. NiMICK/R. PRICE PRESENTATION 11:15-11:30 BREAK 11:30-12:00 LOS ALAMOS NATIONAL D. BROXTON
> LABORATORY PRESENTATION 12:00-12:30
~~ SCIENCE APPUCATIONS S. WOOLFOLK N
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INTERNATIONAL CORP. PRESENTATION 3 12:30-1:00 BREAK TO LOOK AT RAW DATA ALL 1:00-2:00 WRAP-UP DISCUSSION ALL J , n.
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SCIENCE SUPPORT SYSTEM COMMITTEE 1-PARTICIPANTS MEETING
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# N P4 in f-l YUCCA MOUNTAIN PROJECT l
UPDATE MEETING i JUNE, 1988 1 4
!1ARD COPY OF PRESENTA TION VISUALS
, , . . . i L _ _ _ _ _ - _ - ___ _ _ - _ - _
l r YUCCA MOUNTAIN PROJECT l 1 l UPDATE I MEETING I _ )
~
< F 7 l l l l IlfrRODUCTIONS General Public Question and Ansver Session TRANSPORTATION PRESENTATION Public Questiac- and Ansver Session l EARTH SCIENCES PRESEffrATION Public Question and Ansver Session SOCI0 ECONOMICS PRESENTATION Public Question and Ansver Session
I l PURPOSE OF THE PROJECT UPDATE MEETINGS IS TO PROVIDE INFORMATION ON THE YUCCA MOUNTAIN PROJECT THAT THE PEOPLE OF NEVADA HAVE REQUESTED L J F 3 THE REPOSITORY PROJECT IS COMPLEX, AND TO UNDERSTAND THE PUBLIC'S INFORMATION NEEDS, DOE HAS TALKED TO A NUMBER OF NEVADANS AROUND THE STATE TO IDENTIFY AREAS OF CONCERN THEY ARE TRANSPORTATION
. EARTH SCIENCE i
SOClOECONOMICS 1 l L J
F 3 ! e WHY NEVADA? 1 o WHEN WOULD A REPOSITORY BE BUILT? e WHAT'S GOING ON NOW AT YUCCA MOUNTAIN? e WHY SHOULD WE BELIEVE-WHAT DOE SAYS? e WOULD THE REPOSITORY BE SAFE? L J WHY HAS NEVADA BEEN SINGLED OUT FOR A REPOSITORY?
)
1
f 3 e HIGH-LEVEL W ASTE IS A NATIONAL PROBLEM; APPROXIMATELY 15,000 TONS OF COMMERCIAL SPENT FUEL NOW IN TEMPORARY STORAGE AROUND THE COUNTRY e NUCLEAR POWER CURRENTLY PROVIDES ABOUT 17 PERCENT OF U.S. ELECTRICITY, SECOND ONLY TO COAL AND IS ESSENTIAL FOR A BALANCED ENERGY SUPPLY ! e IN DECEMBER 1987, CONGRESS DIRECTED ! DOE TO INVESTIGATE YUCCA MOUNTAIN. IF THE STUDIES INDICATE THE SITE IS SUITABLE, THE LAW REQUIRES DOE, WITH PRESIDENTIAL APPROVAL, APPLY TO THE U.S. NUCLEAR REGULATORY COMMISSION FOR A LICENSE TO CONSTRUCT A i REPOSITORY L J r 7 WHEN WOULD A REPOSITORY BE BUILT? l l l t k _ m____-*.-_.-_.**--w-->ma-- - - --- e- --lew --' e '_w-'--w
f ^ 3 ' l PROGRAM SCHEDULE NOMINCION/ SITE CHARACTERl2ATION i LICENSING CONSTRUCTION / RECOMMEN.'ATION PHASE e PHASE i OPERATIONS PHASE PResso NrAL i i PHASE APPROVAL Siis te PRE SJOENT STARf
- APenc4t3 REPCstTORY h NWPA SITE CONSTRUCTION N.PA l'#4F,CP
- t!'
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Y ty y y t,,,,,,,,,,=t m g TIME NOW g g CONSULTAfivE DR AFT FINAL $ PENT Futt Stit IIS AND HICH LEVEL CHAR At,lT E R12AfiCN 1994 W AsfE ARRIyt$ PLAN (SCP/CD) Af REPOCITORY
,/,8 2M3
( 9 WHAT IS GOING ON NOW AT YUCCA MOUNTAIN? d i t P
F 7 e WORK CONDUCTED OVER THE NEXT i SEVEN YEARS WILL DETERMINE IF A REPOSITORY WILL BE BUILT AT YUCCA MOUNTAIN e APPROXIMATELY $2 BILLION TO BE SPENT DURING SITE CHARACTERIZATION e ABOVE AND BELOW-GROUND STUDIES WILL BE CONDUCTED TO GATHER INFORMATION TO EVALUATE THE SITE e TWO EXPLORATORY SHAFTS AND EXPLORATORY DRIFTS WILL I BE CONSTRUCTED l L J r' 3 WHY SHOULD WE BELIEVE WHAT DO'd SAYS?
' )
DOE /NV ORGANIZATION I WASTE MANAGEMENT PROJEOT OFFICE C. P. G ER TZ SCIENCE APPLICATIONS INTERNATIONAL CORP. TECHNICAL & MANAGEMENT REYNOLDS ELECTRIC.* L SUPPORT SERVICES & ENGINEERING CO.
' HOLMES & NARVER Q_ J.C.CALOVINI MACTEC -
f FENIX & SCISSON J. P. THOMAS R. L BULLOCK l
. us vroAs. Nv *us VEGAS. NV I I I I LAWRP.NCE U.S. GEOLOGICAL SANDIA NATIONAL LOS ALAMOS LIVERMORE SURVEY LABORATCRIES M "L NATIOML O ORY
,_L R. HAYES T. O. HUNTER L D. RAMSPOTT D.T.OAXLEY s DENVEft, CO e ALBUQUERQUE.NM e UVERMORE. CA e LOS AUMOS m-muse PROJECT DIRECTION 00ENv Pue 5 4 as
{ L J f 7 THE NATIONAL REPOSITORY PROGRAM IS ONE OF THE MOST CLOSELY REVIEWED PROGRAMS ljNDERTAKEN BY THE FEDERAL GOVERNMENT THESE ORGANIZATIONS HAVE AN IMPORTANT REGULATORY AND! OR OVERSIGHT ROLE: e NUCLEAR REGULATORY COMMISSION (NRC) e STATE OF NEVADA l NUCLEAR WASTE PROJECT OFFICE COMMISSION ON NUCLEAR PROJECTS
- LEGISLATIVE COMMISSION ON HIGH-LEVEL RADIOACTIVE WASTE
- LOCAL GOVERNMENTS e
NUCLEAR WASTE TECHNICAL REVIEW BOARD NOMINATED BY NATIONAL ACADEMY OF SCIENCES e
- EDISON ELECTRIC INSTITUTE (UTILITIES) e U.S. GENERAL ACCOUNTING OFFICE (GAO) e ENVIRONMENTAL PROTECTION AGENCY (EPA)/ DEPARTMENT OF TRANSPORTATION (DOT) e INDEPENDENT ACCOUNTING FIRM (PEAT MARWICK, MAIN AND COMPANY) k d l _,.,_-,y_ayye- '-,wv=- - - ' - ' - ' - ^ ^ '
F 3 WOULD THE REPOSITORY BE SAFE? l l 1 L J F 7 e REPOSITORY IS DESIGNED TO USE NATURAL AND ENGINEERED BARRIERS TO CONTAIN RADIOACTIVE MATERIALS ( e REPOSITORY WILL NOT BE BUILT UNLESS IT MEETS STRICT NRC REGULATIONS AND EPA STANDARDS WHICH PROTECT PUBLIC HEALTH, SAFETY AND THE ENVIRONMENT
l e ROUTING e SAFETY e CASK DESIGN TRANSPORTATION L J F 7 1 TRANSPORTATION OF REPOSITORY W'ASTE , e PLANNED TO BEGIN IN THE YEAR 2003 e SEVERAL TECHNICAL ISSUES OPEN AT THIS TIME
- CASK DESIGN
- MRS DESIGN
- MIX OF TRUCK AND RAll SHIPMENTS l L )
F 7 i U.S. DEPARTMENT OF TRANSPORTATION HIGHWAY ROUTING RULES CARRIERS MUST USE PREFERRED HIGHWAY ROUTES SELECTED TO REDUCE TIME IN TRANSIT: i 1) AN INTERSTATE SYSTEM HIGHWAY i
- 2) ALTERNATE ROUTES SELECTED BY A "STATE ROUTING AGENCY" l
L J \ r 3 i U.S. DEPARTMENT OF TRANSPORTATION HIGHWAY ROUTING RULES . CARRIERS MUST USE PREFERRED HIGHWAY ROUTES SELECTED TO REDUCE TIME IN TRANSIT:
- 1) AN INTERSTATE SYSTEM HIGHWAY
- 2) ALTERNATE ROUTES SELECTED BY A "STATE ROUT!NG AGENCY"
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INDIAN TRIBAL AUTHORITIES HAVING POLICE POWERS TO REGULATE AND ENFORCE HIGHWAY ROUTING REQUIREMENTS ARE INCLUDED IN THE DEFINITION OF "STATE ROUTING AGENCY" L J
A (RAIL ' ROUTES e RAll SPUR IS NECESSARY TO CONNECT THE UNION PACIFIC, SANTA FE OR SOUTHERN PACIFIC TO THE SITE e STUDY FOR ALTERNATE RAll SPURS UNDER WAY l t i i SHOULD RAll SPUR BE AVAILABLE FOR JOINT USE? DOE HAS ALLOWED BUS!NESSES TO USE RAll SPURS AT OTHER SITES i - SHARED COST
- COMPATIBLE ACTIVITIES 1 .
b 7
/
64 CASK 1
\
f' DESIGN ~ ~ " "'(
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us ,ie.o .u==.o= / 1%','T:f;' ..., I.'uYE"= init c... see,
# e VARIOUS CASK
,un,t,o.i.in su . .tr DESIGNS ARE
. ." UNDERWAY TO s ? '
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. 7.L'"e'ic""*"'s u- na NUMBER OF
/[.......,,SE. '_... .~o ouir coviaSHIPMENTS
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e e CASKS WILL BE CERTIFIED BY THE NRC A F 3 3 PHOTOGRAPHS A. SEQUENTIAL REQUIREMENTS FCR CASKS (SCHEMA TIC) B. CASK FIRE TEST C. CASK DROP TEST l l l l l Y l_--__
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F , 1 1 INSPECTION AND ENFORCEMENT l l i SAFETY l P i i d
ACCIDENT PREVENTION e ENFORCE REGULATIONS e DRIVER TRAINING e EQUIPMENT MAINTENANCE : AND INSPECTION L J SAFETY CHECKS ARE MADE l e UPON DEPARTURE e AT STATE BORDERS (IF DESIRED) e UPON FINAL DESTINATION
f 3 i EMERGENCY RESPONSE . e POLICE, FIRE FIGHTERS e NEVADA DEPT. OF HEALTH, ; RADIATION SECTION e DIV. OF EMERGENCY MGMT. t e DEPARTMENT OF ENERGY ! L J f -~ m i DOE / NEVADA l EMERGENCY RESPONSE SUPPORT i e AGREEMENT WITH STATE AGENCIES TO RESPOND TO INCIDENTS INVOLVING RADIOACTIVE MATERIALS e RADIOLOGICAL ASSISTANCE TEAM AND ITS RESNIRCES
~
e PROVIDES TRAINING PROGRAM TO l HIGHWAY PATROL, FIRE-FIGHTERS, AND EMERGENCY MEDICAL PERSONNEL i
PHYSICAL PROTECTION SYSTEM i 1
- NRC APPROVAL OF ROUTE e SPECIFIED PROCEDURES e COMMUNICATIONS CENTER e PROVISION OF AT LEAST ONE ESCORT e ADVANCE ARRANGEMENT WITH LOCAL LAW-ENFORCEMENT AGENCIES e VEHICLE IMMOBILIZATION 1
L J F 3 TRANSPORTATION OF COMMERCIAL SPENT FUEL HAS AN EXEMPLARY RECORD ' IN MORE THAN 20 YEARS OF SHIPPING COMMERCIAL SPENT FUEL IN THE UNITED STATES, NO ACCIDENT HAS CAUSED A RELEASE OF RADIOACTIVE MATERIAL e i k
( 7 3 DOE /NV TRAINING PROGRAMS e HIGHWAY PATROL TROOPERS HAVE RECElVED RADIOLOGICAL EMERGENCY RESPONSE TRAINING (442 SINCE FY 1981) e FIRST ON-SCENE COURSE FOR FIRE FIGHTERS HAS BEEN ATTENDED BY 458 PERSONS SINCE FY 1981 e THE EMERGENCY MEDICAL PERSONNEL RADIOLOGICAL SEMINARS HAS BEEN ATTENDED BY 683 PERSONS SINCE FY 1981 e THE RADIOLOGICAL EMERGENCY RESPONSE COURSE FOR THE RADIOLOGICAL EMERGENCY RESPONSE TEAMS HAS BEEN ATTENDED BY AN UNKNOWN NUMBER OF STATE OF NEVADA PERSONNEL k I l OCRWM TRANSPORTATION PROGRAM FUNCTION LEAD RESPONSIBILITY POLICY AND MANAGEMENT DOE HEADQUARTERS NEVADA TRANSPORTATION DOE NEVADA OPERATIONS OFFICE OPERATIONS PLANNING OAK RIDGE NATIONAL LABORATORY ! CASK & VEHICLE IDAHO NATIONAL ENGINEERING DEVELOPMENT LABORATORY INSTITUTIONAL & DOE CHICAGO OPERATIONS OFFICE ECONOMIC ANALYSIS i k i
SOClOECONOMIC l QUESTIONS : 1 L J F 7 4 e EMPLOYMENT e EXPENDITURES e POTENTIAL IMPACTS e FINANCIAL ASSISTANCE l--_ ..
r 3 WHAT ABOUT EMPLOYMENT ' DURING SITE CHARACTERIZATION? l Y Y I ABOUT 60% OF YUCCA MOUNTAIN PROJECT ' WORKERS LIVE IN NEVADA r Muusotof stao J Pe asumo
/ : : \ ** 8 8 P'ha I Cmuncmts E q
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=?gA l w=enat 6%
asuaastoa g,,cogn n<c a 02% l 9 . 4 t. rv 0.4% IN OTHER NEVADA COUNTIES
DURING SITE CHARACTERIZA-TION, YUCCA MOUNTAIN PROJECT WORK FORCE IN NEVADA COULD PEAK AT ABOUT 1400 L J f 7 REPOSITORY DESIGN WILL CONTINUE UNTIL 1995 l EMPLOYMENT ESTIMATES WILL BE ; REVISED AS DESIGN PROGRESSES
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ESTIMATES OF EMPLOYMENT IN NEVADA WERE MADE RECENTLY FOR INCLUSION IN REPORT TO l CONGRESS AT END OF 1988 k _ _ ./
1 l f ESTIMATES OF EMPLOYMENT IN NEVADA DURING CONSTRUCTION OF A REPOSITORY AT YUCCA 3c00 MOUNTAIN AND WASTE EMPLACEMENT 2850 " 2800 AT PEAK OF CONSTRUCTION 2!00 2550 2400 2250 1965 AT PEAK OF WASTE EMPLACEMENT 1950 1800 E y 1650 1500 1350 I200 TO CARETAKER AND DECOMMISSIONING 0$0 TO SITE CHARACTERIZATION 8 - tese 2000 20c2 2004 2004 2004 2010 20t2 2 014 20 5 20ta 2020 202.2 2024 2025 7999 2001 2003 2005 2007 2001 2011 20t3 20:3 2017 2079 2021 2023 2023 202 i 7 WHAT ABOUT EXPENDITURES? i e YUCCA MOUNTAIN PROJECT ANNUAL EXPEN-DITURES ARE CURRENTLY ABOUT $104 MILLION. i ABOUT $57 MILLION OF THAT IS SPENT IN NEVADA e YUCCA MOUNTAIN PROJECT EXPENDITURES THROUGH 1995 COULD REACH $2 BILLION e DURING REPOSITORY CONSTRUCTION, ANNUAL WAGE PAYMENTS COULD BE UP TO S95 MILLION IN NEVADA e DURING WASTE EMPLACEMENT, ANNUAL WAGE PAYMENTS COULD BE UP TO $55 MILLION IN NEVADA k
WHAT ABOUT POTENTIAL IMPACTS? l l l . , , I l DOE STUDIES TO DATE HAVE NOT IDENTIFIED ANY POTENTIAL SIGNIFICANT ADVERSE . SOClOECONOMIC IMPACTS
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- _ _ _ . . - . . = . - _-- __-___ - - -. . -- . - _ _ _ _ - - _ - - . - - .
i I 7 I DOE IS CONTINUING l SOClOECONOMIC STUDIES i DURING THE SITE #w$.,
.s j s,.:',';;,,,,, f W ... j l
CHARACTER 12ATlON ' " PHASE, DOE IS / MONITORING THE M e ONot NUMBER, SKILLS, *c 4n o AND RESIDENTIAL #
- 8're caljd* ' ' 4 "o n LOCATION OF YUCCA "**4 rio u MOUNTAIN PROJECT ""'$ $~ .
t ' WORKERS '<~u,,,""
* ~,. ,*,:-lll;;. ... , _
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e W J F 7 e REPORT TO CONGRESS WILL ADDRESS POTENTIAL IMPACTS OF LOCATING A t REPOSITORY AT YUCCA MOUNTAIN i e WILL ANALYZE RESPONSIBILITIES FOR DEALING WITH IMPACTS
- FEDERAL GOVERNMENT
- STATE GOVERNMENT
- JOINT i
l e RECENTLY MEET WITH EXPERTS IN
' - NEVADA STATE AGENCIES
- CLARK COUNTY
- NYE COUNTY
- LINCOLN COUNTY
- ESMERALDA COUNTY N ]
I
" *O'* " " ** _
m _ _, WHAT ABOUT POTENTIAL IMPACTS ON TOURISM? l L d 1 I 7 WHAT ABOUT POTENTIAL IMPACT ON TOURISM? e "CASE STUDIES" OF EVENTS IN AREAS WHERE TOURISM WAS AN IMPORTANT PART OF THE ECONOMY WERE CONDUOTED BY DOE e SOME OF THESE STUDIES LOOKED AT
- POTENTIAL VOLCANIC ACTIVITY NEAR MAMMOTH LAKES, CALIFORNIA
- LOVE CANAL, NEAR NIAGARA FALLS, NEW YORK
- LAS VEGAS HOTEL FIRES
- NEVADA TEST SITE e CONCERNS ABOUT LONG-TERM NEGATIVE EFFECTS WERE EXPRESSED DURING THE EVENTS e MEASURES OF LOCAL TOURISM ANALYZED FOR CASE STUDIES SHOWED NO LASTING EFFECTS N ]
. f l WHAT ABOUT FINANCIAL ASSISTANCE?
e DOE MAKES GRANTS TO THE STATE OF NEVADA TO PARTICIPATE IN THE REPOSITORY SITING PROCESS AND CONDUCT INDEPENDENT STUDIES. THE STATE, IN TURN, PASSES FUNDS THROUGH TO LOCAL GOVERNMENTS IN SOUTHERN NEVADA e FUNDS ARE ALSO PASSED THROUGH TO THE UNIVEPSITY OF NEVADA SYSTEM e DOE WILL HAVE COOPERATIVE AGREEMENT WITH UNIVERSITY OF NEVADA SYSTEM e AMENDMENTS TO THE NUCLEAR WASTE POLICY ACT IN 1987 MADE SOME COUNTIES ELIGIBLE TO APPLY FOR GRANTS DIRECTLY
- k _
J F 3 l e DOE TO MAKE TAX-LIKE PAYMENTS l EQUAL TO THOSE A PRIVATE FIRM WOULD PAY IN ACTUAL TAXES WHILE UNDERTAKING REPOSITORY SITING CONSTRUCTION AND OPERATION e DETAILS WILL BE FINALIZEO THIS SUMMER e PAYMENTS TO BEGIN IN EARLY 1989 e PAYMENTS-EQUAL-TO-TAXES WILL CONTINUE THROUGH LIFE OF YUCCA MOUNTAIN PROJECT L J
, I l SOClOECONOMICS BACK UP l
l l L ) ( I l SECTION 175 REPORT TO CONGRESS WILL c INCORPORATE INFORMATION GATHERED FROM ! LOCAL EXPERTS l l e STATE OF NEVADA
- NEVADA NUCLEAR WASTE PROJECT OFFICE
- TOURISM COMMISSION ;
- ECONOMIC DEVELOFMENT COMMISSION !
- DEPARTMENT OF MINERALS
- DIVISION OF EMERGENCY MANAGEMENT
- EMPLOYMENT SECURITY DIVISION
- DEPARTMENT OF TRANSPORTATION
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- NEVADA MINING ASSOCIATION i
- BUREAU OF RADIOLOGICAL HEALTH, DEPARTMENT OF HEALTH
- FIRE MARSHAL'S OFFICE
- EMERGENCY MEDICAL SERVICES k
. . a
7 SECTION 175 REPORT TO CONGRESS WILL INCORPORATE INFORMATION GATHERED FROM LOCAL EXPERTS l (CONTINUED) l e CLARK COUNTY COUNTY PLANNING DEPARTMENT
- BOULDER CITY PLANNING DEPARTMENT
- HENDERSON CITY NUCLEAR WASTE PLANNING OFFICE
- CITY OF LAS VEGAS DEPARTMENT OF ECONOMIC AND URBAN DEVELOPMENT
- NORTH LAS VEGAS DEPARTMENT OF PUBLIC WORKS NEVADA DEVELOPMENT AUTHORITY CLARK COUNTY SCHOOL DISTRICT
- LAS VEGAS CONVENTION AND VISITORS AUTHORITY l - UNLV BUSINESS AND ECONOMIC RESEARCH CENTER NELLIS AIR FORCE BASE
- NEVADA POWER COMPANY
- OFFICE OF ENERGENCY MANAGEMENT l
L J f 3 . SECTION 175 REPORT TO CONGRESS WILL INCORPORATE INFORMATION GATHERED FROM LOCAL EXPERTS (CONTINUED) e NYE COUNTY
- COUNTY COMMISSIONERS
- AMARGOSA VALLEY, BEATTY AND PAHRUMP ECONOMIC DEVELOPMENT COMMITTEES
- TONOPAH CHAMBER OF COMMERCE
- CAL-VADA
- CENTRAL NEVADA DEVELOPMENT AUTHORITY
- OFFICE OF EMERGENCY MANAGEMENT C
SECT!ON 175 REPORT TO CONGRESS WILL INCORPORATE INFORMATION GATHERED FROM LOCAL EXPERTS (CONTINUED) l e LINCOLN COUNTY
- COUNTY COMMISSIONERS
- CALIENTE COMMUNITY DEVELOPMENT DEPARTM.
- LINCOLN COUNTY ECONOMIC TASK FORCE
- LINCOLN COUNTY /CALIENTE JOINT IMPACT ALLEVlATION COMMITTEE e ESMERALDA COUNTY
- COUNTY COMMISSIONERS e OFFICES OF EMERGENCY MANAGEMENT IN CHURCHILL, ELKO, EUREKA, HUMBOLT, LANDER, LYON, MINERAL AND PERSHING COUNTIES L _
J r 3 ABOUT 190 PERSONS (WORKERS AND THEIR FAMILIES) HAVE MOVED TO NEVADA
, -., SINCE MAY,1986 t ,. .. .i r i i 9p t .. nei. t 1
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r 7 EARTH SCIENCES e GEOLOGY & HYDROLOGY
.e PLANS FOR SITE CHARACTERIZATION i
f 3 SITE PROGRAM l GEOCHEMISTRY ROCK CUMATE NEAR/FAR PROPERTIES ) HYDROLOGY GEOLOGY TECTONICS METEOROLOOY F1 ELD SEALS I
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42 6 10 $ 6 9 3 INVESTIGATIONS 107 20 17 30 9 20 11 l STUDIES AC TIES 57 41 102 27 53 28 l Ah%e8l? MJ64 ism
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PERFORMANCE & DESIGN PROGRAMS PERFORMANCE ASSESSMENT DESIGN PRECLOSURE POSTCLOSUR2 PRECLOSURE POSTCLOSURE 23 ISSUES 6 9 5 3 13 lNFORMATION 1.* 27 18 15 NEEDS 122 ACTMTIES 23 46 22 a k _. J F 3 l l l t l For more information on the repository progre r. write or call: l Office of Civilian Radioactive Office of Exterriel Affairs l Waste Managerent U.S. Department of Energy U.S. Cepartment of Energy Nevada Operations Office Mail Stop RW.43 P.O. Box 98518 Washington. O.C. 20585 Las Vegas, NV 69193 8518 (202)S86 5772 (702) 295 3521 E 9
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J #M United States Department of the Interior i e GEOL (X;1 CAL $URVEY
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BOX 25N6 M S 421.. __ DENVER FEDFRAL CENTER l DENVER, COLOR ALO 8022000# na,.,,,,,.i., June 30,1988 Uel S. Clanton Waste Management Project Office U.S. Department of Energy P.O. Box 98518 Las Vegas, NV 89193 8518
Subject:
WMPO Action Item 88-1656
Dear Uel:
Enclosed is . list of cureboles and Intervals that have been identified as : possible candidates for implementing yet to be determined "qualification procedures". On the basis of the following criteria the enclosed table outlines the Survey's list of priorities as currently perceived. The two major stratigraphic intervals that we have selected are the Topopah Member of the Paintbrush Tutt and the tuffaceous beds of Calico Hills. The Spring interva !S include the host rock and the potential barrier between the repository the water table, respectively. Characterization of samples from these intervals are considered a high priority. Other considerations are intervals that include contacts between subjacent stratigraphic units, which help estabinh the primary geometric configuration of the repository area. We have included only con'Jnuously cored holes in this selection process. Although all holes where geophysical logs and bit cutting samples have been collected represent an integral subset of data for establishing the geologic framework of Yucca Mountain, continuous'y cored holes have provided the fundamental reference data set, from which reliable lithcIngi: and geophysical correlations are made. I Coreholes that penetrate the above mentioned stratigraphic units within or near the area enclosed by the perimeter drift are presently considered more important for later use in licensing interactions ed are giv:n a higher priority. Sine ly, W
/4 12rry R. Hayes Technical Project Officer U.S. Geological Survey 1
cc: USGS RC/1.2.9.3/ Drill hole samples, Qualification J. Blaylock, DOE /WMPO R.B. Raup, USGS/ Denver 1
,l' Priority List of Core for "Qualification"
., Depth interval Analy sis /Dat a Borehole . (in_ feet) produced Priority - 1 (Topopah Spring Member) USW G-4 203-1410 Lithologic description and correlation USW 0-1 210-1425 Do. UE25A-1 245-1389 Do. 400-1430 USW GU-3/G-3 Do. USW G-2 734-1725 Do. Priority 2 (Tuff aceous Beds of Calico Bills) USW G-4 1410-1786 Do. USW G-1 1425-1826 Do. UE25A-1 1339-1861 Do. USW Ctf-3/03 1430-1532 Do. USW G-2 1725-2729 Do. USW G-4 123- 173 Do. 173- 253 Do. 1736-1786 Do. 2219-2269 Do. 2730-2780 Do. USW G-1 35- 210 Do. 1776-1826 Do. 2148-2198 Do. 2614-2664 Do. 3533-3583 Do. 3920-3970 Do. 4915-4965 Do. 5295-5345 Do. 5409-5459 Do. UE2 5A-2 1811-1861 Do. 2308-2358 Do. , 2475-2500 Do.
O Depth interval Analysis / Data B_o r e hole (in fset) p rodu_c ed Friority 3--continued USW GU-3 344- 400 Do. 1532-1584 Do. 1965-2030 Do. 2608-2667 Do. USW G-3 2608-2634 Do. 3848-3901 Do. 4846-4908 Do. USW 0-2 200- 275 Do. 316- 366 Do. 473- 523 Do. 2704-2729 Do. 3223-3315 Do. 3477-3599 Do. 3889-3939 Do. 4170-4220 Do. e 4
w ~k I United States Department of the Interior GEOLOGICAL Sl'RVEY BOX 25016 .\l.S. 4 21 p DENVER FEDERAL CENTER 9[tq _,,,__g/727_ DENVEP. COLORADO 80225 C
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ss21-r2: May 12, 1988 . gg/ g
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, L.. UQ Uel S. Clanton Waste Management Project Office -
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U.S. Department of Energy " P.O. Box 98512 Las Vegas, N1 89193-8518 j,4 2 card
SUBJECT:
Identify the Need to Qualify Existing Samples (WMPO Action Item 88-1656) re: WMPO: USL-1806
Dear Uel:
Carl Gertz' letter of May 2,1988, on the above subject directs the Geological Survey and the other NNWSI participant organizations to provide you with a list of existing NNWSI drill hole samples that we perceive could be used as a basis for licensing data or may become the source of primary licensing data in the future. In response, the USGS position is that we do _ perceive of any subset of samples that can be so identifP Virtually all of the existing core and bit cuttings were used in the preparation of lithologic logs which were published or will be published in drill hole basic data reports. These data reports, in turn, have been and will continue to be used and referenced in our interpretative reports, position papers, and NNWSI licensing documents. We cannot determine that any specific sample will or will tiot play a part in the licensing process. In fact, every existing sample is susceptible for selection as the basis for some scientific interpretation, analysis, or conclusion that can be used in support of, or against, licensing. Therefore, unless you intend to exclude all USGS, drill hole basic data reports from the licensing process all drill hole samples, including core, cuttings, and water from either tic' saturated zone or extracted from rocks of the unsaturated zone, should be censidered as candidates for qualification. Because of the critical naturn of this subject and the long-term consequences of any pertinent decisions, I propose that the matter be put on the agenda for PM/TPO discussion and action as soon as possible. Please contact me or Craig Bentley if you wish to discuss this subject further. Sincerely, ACTION &M INFO dy B. 4 AMA Larry R. Hayes J AMESH Technical Project Officer NNWSI l AMOE u.S. Geological Survey CER n n :a copy L _
.~ - ..- .. - . . - , _ .
cc: 'USGS RC/1.2.9.3/NT/ Drill hole samples, Qualification
'C.P. Gertz, DOE /WMPO J. Blisylock, DOE /WMPO T. Hunter. SNL, Albuquerque, NM M. Spaeth, SAIC/LV D. Oakley, SANL, Los Alamos, NM L. Ramspott, LLNL, Livermore, CA cR.B. Raup, USGS/ Denver D.C. Gillies USGS/ Denver J.R. Willmon USGS/ Denver C.B. Bently USGS/ Denver LRH/CBB/mt-05880017 c
l
- 1. :
l l AWRENCE IJVERMORE LABORATORY NWM:88-101 Uel S. Clanton May 31,1988 Waste Management Project Office U.S. Department of Energy P.O. Box 98518 Las Vegas, NV 89193-8518
SUBJECT:
Identify the Need to Qualify Existing Samples (WMPO Action Item 88-1656) re: WMPO: USL-1860
Dear Ucl:
Although we have received core or cutting samples from various depth intervals in eight drill holes on or near Yucca Mountain and have used some of the material in experiments, none of these samples need to be qualified if repository horizon samples become available in a timely manner. However, if some QA Level I drill hole samples are not available for our use on or about ! July 1989 and larger samples are not available from the repository horizon of the exploratory shaft on or about 1 September 1990, we may need to qualify samples trom the I existing drill holes in order to meet project deadlines. Sincerely yours, b* David Short l Deputy Technical Project Officer for NNWSI ACTION cc: D. Emerson D N CC. W. Glassley CC: 2 N o>w J s CC: M4d_ W. O'Connell CC. R. Aines CC: - J. Dronkers CC: FIEC' o AnEqavCnxinnryE~txw thswsnyof CatWr>3 Po60s B06 Lenoe Castma 94SSO Teannc(41SJ422 tt00 Tws 910-)S0 83)9 UCLLL LVMR RECOP&JWD
ACTICN O/I/d Sandia National Laboratories INFO ~ ~ . ~ ~ ~ 8"85 AMA AMESH ny n y AMOE 0ER A MN - - C0/Az2mm 0bW Uel S. Clanton CU Waste Management . Project Office CC; # -- U.S. Department of Energy Nevada Operations Offica CC; - -' - P.O. Box 98518 CO- _ . . . . . - Las Vegas, Nevada 89193-8518 C-- -
Dear Uel:
K.'.,;..-"
Subject:
Response to letter dated 5/2/88 from Gertz to TP0s regarding the qualification of existing samples (WMPO Action Item 88-1656) This letter is SNL's response to the request in the subject letter "to provide a list of any existing samples that the participants perceive could be used as a basis for licensing data or may become the source of primary licensing data in the future." Our position for core samples that have been scored in the USGS core library and for surface-outcrop samples that were collected and stored by SNL will be discussed separately. The plans for future SNL testing that appear in the SCP were developed assuming that samples taken from existing coreholes would not or could not, in general, be qualified for obtaining orimarv data for licensing. Existing data and data from ongoing activities with ' unqualified" core may, as necessary, be used as supporting or corroborating information in the licensing process. Our plans for obtaining primary data require samples from new coreholes at Yucca Mountain and mosc of our requirements are for samples from locations that have not been previously cored. Therefore, we cannot identify a specific s ubset of existing core that, if qualified, would significantly change our requirements as expressed in the SCP. If the planned drilling were greatly reduced, the reduction might force us to attempt to use existing core for gathering future primary data. The nature of such a redaction would dictate our specific qualifying requirements. Since your request does not specify such contingencies, we cannot identify a subset of core for possible qualifying. Also, the available core, if qualified, could satisfy only a fraction of our future sample requirements and the effort and cost, if qualificatien is indeed possible, would probably exceed that of obtaining new core. In addition to qualifying unused core, if samples that were used to obtain eristing data were qualified (assuming this is possible), qualifying existing data as primary data would require the qualification of the testing methods, procedures, etc. , which may not be possible, Therefore, we believe that it is more prudent to plan to use existing data as possible supporting or corroborating information but not as part of a primary data base.
. IlECORO Copy
1
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i ! j i U. S. Clanton -2 MAY $ 7 ggg l 1 l Out surface outcrop samples, which are from Busted Butte, were gathered, i transported, and. stored under SNL direction. Our records on these samples seem to be sufficient to support their use for *ork at any quality level. We will begin using these samples for QA Level 1 oc 2 work if, af ter thoroughly reviewing our records, we are satisfied that the documentation is-adequate. However, we expect to qualify the use of these samples without significant project support. Any questions about our sample requirements shoula be directed to Tom Blejwas (PTS 846-0541) or Ron Price (PTS 844-8980). Sincerely, g&p v - ~ k& Thomas 0. Hunter,Itanager i NNWSI Proj ect Department 6310 TEB: 6313 :nj h Copy to: 6310 T. O. Hunter 6310 R. R. Richards 6313 J. T. George 6313' F. B. Nimick 6313 R. H. Price 6313 B. M. Schwartz 6315 S. Sinnock 6315 C. Rautman 6313 T. E. Blejwas , 6310 10/124213/COR/NQ 6310 10/1293/COR/NQ 6310 NNWSICF
i 3""* o tS88 OSASMOS ESS-1, Geology / Geochemistry i i Los Alamos Nat.onalLaboratory MS 0462 ) Los Alamos.New Mexico 87545 (505) 667-6879 TWS-ESS-1-6/88-10 , Page 1 of 2 ACTION cc ON M'7M Uel Clanton CC: M#M - ACTION ue Waste Management Project OfffG C: /-/agh 0 E"*'9Y cc # # # #29 AMA S'.o'.$$*$i8 ~ Las Vegas, NV 89193-8518 CC: #### AMESH CC M _._. AM0E-Through: Don Oakl h
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Dear Uel:
SUBJECT:
IDENTIFICATION OF KEY CORE INTERVALS FOR LICENSING This letter is in response to Carl Gertz' letter of May 2, 1988 requesting that we identify key intervals in existing drill core from which information will be required for licensing. As I discussed with you in our telephone conversation of May 23, this is not a simple and straightforward task. Key intervals from specific cores can be identified for the alteration hi story and tracer evaluation studies. However, our work on the mineralogy of transport pathways and fracture mineralogy requires characterization of all units across the repository block and along potential groundwater flowpaths to the accessible environment. To do this, a complete three-dimensional picture of the mineral distributions at Yucca Mountain must be constructed. We feel that use of limited subsets of the existing data will not be adequate to document the many changes in mineralogy that occur vertically and laterally. at Yucca Mountain. Broxton and Vaniman describe the impact of disqualifying data collected for existing core for Min / Pet studies in Attachment 1; this information was provided to the core steering committee in August 1986.. We think a more profitable approach is the one suggested by the
- steering committee, that is to use scientific evidence rather than a i
paper trail to validate the core and the results of analyses done on it. My memo of October 16, 1987 to Steve Leedom (Attachment 2) describes briefly our position on the use of existing core. The ideas outlined in categories 1 and 2 of that memo are discussed in more
- detail in Attachment 3.
t Key intervals can be identified for the studies given under categories 3 and 4 of that memo. S. Levy will send you the list she is compiling of key intervals for the alteration history activity. l An Equal Cooortunity Emoeoyer/ Operated ey tre Uneversity of Canfoma RECORO COPY + .-
I Uel Clanton June 10, 1988 TWS-ESS-1-6/88-10 Page 2 of 2 The key intervals for the tracer evaluation study are core Ve25 c-1: 1515 to 1525 ft, 2342-2352 f t, and 2603-2613 ft, and core Ve25 c-2: 1623-1643 ft, 2402-2412 ft, and 2520-2530 ft. Waxed core may be available for some of these intervals. No core has been used in this study yet, but_ samples have been re It is not necessary to know the exact depth on these cores. quested. It is necessary to be able to demonstrate that the intervals packed off for the USGS tracer flow-tests are the same ones used in the tracer evaluation studies. This might be accomplished by the use of borehole televiewer logs for identifying fractures or other distinguishing features, but I am not familiar enough with this core or the logs to be certain. Sincerely, habu. p Barbara Carlos BC:mj Att, a/s Cy: J. Blaylock, WMPO (w/att.) J. Canepa, N-5 (w/att.), MS J:21 K. Thomas, INC-11 (w/att), MS J514 B. Crowe, INC-11 (w/att.), MS J514 E. Spr' 'ger, MSE-12, J495 D. Croxton, ESS-1 (w/att.), MS D462 D. Bish, ESS-1 (w/att), MS 0469 S. Levy, ESS-1 (w/att.), MS 0462 D. Vaniman, ESS-1 (w/att), MS 0462 CRM-4, MS A150 ESS-1 File RPC File, MS J521 (w/att.) ESS-1 TWS Resident File, MS 0462 (w/att.)
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Attachmsnt 1 Page I of 6 re L MEMO TO THE STEERING COMMITTEE FOR THE USE OF EXISTING OATA COLLECTED FR ORILL HOLES AND ORILL CORES AT YUCCA MOUNTAIN Subj ect: Magnitude of the problem and programatic impact of unacceptable samole traceability for core, cuttings, and water samoles I, Magnitude of the Problem A. List of tests using data from these samples:
- 1) Groundwater Chemistry (WRS 2.3.4.1.1. A) a) Water analyses of samples pumped from wells.
! 2) Sorption and Prect oitattun (WBS 2.3.4.1.5.A)
- a) Sorotton data collected on drill core samples.
31 Oynamic Transoort Processes (WBS 2.3.4.1.6.A) a) Fracture flow experiments on core samples. b) Crushed column tracer studies. c) Matrix di f fusion studies.
- 4) Retardation Sensitivity Analysis (WBS 2.3.4.1.7. A) a) Modeling based on the results of tests 2a, 3a. 3b. 3c, So, and Sc.
- 5) Mineralogy and Petrology of Tuf f (WBS 2.3.4.2.A) a) Quantitative x-ray di ffraction analyses.
b) Petrographic analyses. c) Fracture mineralogy studies. d) Alteration history studies. e) Rock and mineral chemistry' studies. l - f) Mineral stability studies.
- 6) Solubility Detennination (WBS 2.3.4.1.4. A)
- al Solubility measurements.
- 7) Tectonics and Volcanism (WBS 2.3.2.3.1. A)
- a) Volcanology data from core samoles.
l
- 8) Hydrothemal Geochemistry (W8S 2.3.4.1.3. A) l a) Conceptual model of Yucca Mountain development.
. (;.d
Aetachment t Page 2 of 6
- 8. Ort 11 Holes and ~ numbers of samples for each test:
Test: la 2a 3a 3b 3c 4a 5a Sb Sc Sd Se Sf 6a 7a J-J2 w 11 w >750 70 37 20 w J-13 UE-25a#1 w >550 95 80 24 UE-25b81 w 64 30 22 UE-250#1 w 160 52 18 UE-29a#2 w USW G-1 w >500 420 101 14 121 8 USW G-2 w >125 150 101 44 68 11 USW GU-3 w >200 115 81 7 9 9 USW G-3 w 26 130 28 12 24 3 USW G 4 w >550 210 95 260 16 4 USW H-1 w USW H-3 w 22 8 2 USW H-4 w 27 8 5
', USW H-5 w 30 17 9 USW H-6 w 19 19 4 6 6 5 USW YH-1 t
12 14 5 l USW VH-2 l , USW WT-1 21 USW Wi-2 33 l 1 i w . wate, sa.ol., 0 0 4 4
Attachmant 1 Page 3 of 6 C. Sensitivity of each test to samole depth or location la) + 50 ft 2a) None 34) 3b) 3c) 4a) Accurac/ of Yucca Mountain model deoendent on accuracy of data. Sa) + 20 ft 5b) + 20 ft Sc) + 20 ft 5d) + 50 f t Se) ; 50 ft 5 f) 1100 f t
- 68) None 7a) + 20 ft 8a) Only as it would a f fect data from Sa-Se.
D. Sensitivity of each test to chemical modification before testing la) Water chemistry would be affected by chemical modification. 2a) See Sa. 3a) 3b) 3c) 4a) Model is sensitive only as inout from 5 is a f fected. Sa) Possible carbonate loss to HC1; loss of any soluble minerals to drilling fluid. , 5b) None Sc) Possible sourious chloride minerals from HC1; loss of any soluble minerals to drilling fluid. 5d) None t Se) Possible sourious C1 analyses due to El 5f) None 6a) Changes in water composition due to chemical modt fication could change solubilities l 7a) None l.' 8a) Only as it would affect data from Sa-Se. l ;
'f i -
1 Attachment i !
!! PROGRAMMATIC IMPACT Page 4 of 6 A. Cost to duplicate tests if they must be repeated la) 200 K/wel) 2a) 1800 K 3a) 3b) 3c) da) 1500 K Sa) 1800 K Sb) 1800 K Sc) 200 K Sd) 600 K 5e) 600 K 5 F) 500 K
- 64) 300 K 7a) 200 K Ba) 100 K B. Time required to duolicate tests if necessary la) 1 month /well 2a) 4 years 3a) 3b) 3c) 4a) 2 years Sa) 5 years Sb) 4 year, Sc) 1.5 years Gd) 3 years Se) 4 years 5f) 5 years
- 68) 2 years 7a) 8 months Sa) 6 t'onths
Atrachment 1 Page 5 of 6 C. Impact of duplicating tests on present schedule la) 1.5 years delay 2a) 5 year delay 3a) 3b) 3C) 4a) 2 years delay Sa) Sb) Sc) 5d) Ouolication of tests Sa - 5f would delay schedule by 5 years Se) S f) 6a) Ouolication of tests 2 year delay - 7al 8 months delay l 8a) 6 months delay O. Other than duplication. are there alternate methods for producing equivalent test data? There &re no equivalent methods that we know of for producing Sny of these da ta , in one av or another these data must be used in ifcensing. Instead of l issuing a blanket condemnat!on cf all previous data collected from core samoles as not being of quality level 1, it would be crudent to distinguish those studies where: ! (a) Sample location is insignificant, and it !s the geochemical nature of l the sample that is important in apolying the test results (2a, 3a, 3b, 3c, Sf) . (b) Sample location is not a known problem at this time (test la). (c) Samole location oroblems are not primary but are inherited in the usa of data where sample location is important (test 4a). This leaves only tests Sa-Se as irnediate concerns for the t;eering committee. In order to use these data and the models based on them, it will probably be necessary to use the options allowed for in the NRC Oraft Generic
I i Aetachment 1 Page 6 of 6 Technical Position on Qualification of Existing Data for High-level Nuclear Waste Repositories: (a) Peer review of existing data obtained fran cores to judge whether the results obtained make geologic sense. There are. many trends in stratigraphy, petrology, mineralogy, and structure that constrain the sample relations regardless of the concern over sample locations. (b) Depending on the outcome of peer review, confirmatory testing by the drilling of one or a few ouality level 1 drill holes may be reoutred. Data are in hand to fo rmul a te predictions of what should be ' encountered by such drilling in terms of s tra tigrap hy, c:trology, mineralogy, and structure. l l l l l l
/
c,,
. Attachmsnt 2 Paga 1 of 3
= S 8M S i NS 0462 log ochemistry Los Alamos NationalLaboratory Los Alamos.NewMexco87545 (505) 667-6879 TVS ESS-1-10/87-21 Steve Leedom Waste Management Project Office -
P.O. Box 98518 Las Vegas, NV 89193-8518
Dear Steve:
It appears that we can divide our work here into four categories as applies to the level of information needed on the core used in QA level 1 studies:
- 1) Identification by lithologic unit only ~ '
- 2) Identification by drill hole and lithologic unit
- 3) Identification by c-drill hole and interval to be used in tracer test
- 4) Identification by drill hole, lithologic unit and depth.
- 1) Identification by lithologic Unit only Sorption Studies (Thomas)
Samples are characterized by mineralogy before sorption studies, and results are tied to mineralogy. Stratigraphic unit can be determined independently by examination of core. Particular hole is not important. Dehydration Studies (Bish, Vaniman) Requires vitrophyre samples which are int'ependently identifiable by lithologic characteristics. Samples can be chemically characterized by XRF. Particular hole not important, thougn ma,.erial from several holes is desired.
- 2) Identification by lithologic unit and drill hole Mineralogy across Yucca Mountain (Bish)
Chemical variation across Yucca Mountain (8roxton) Stratigraphic and lateral variability of Topopah Spring Member (Byers) Fracture mineralogy (Carlos) All these studies address lateral variability across the repository block and between it and the accessible environment . Therefore these studies require samples identified by drill hole and approximate d!pth. Many samples are examined, so interpretations are based on a suite of A m t over Cocor'wan E +cao,eaCoet reo e, me um er &ry or Cawo,a a A
. Attachmant 2 Page 1 of 3 b Steve Leedom October 15, 1987 samples rather than single occurrences. Hisplacement of one or two samples would have no effect on results. Interpretations are tied to lithology (independently verifiable) as well as depth.
- 3) Identification specific to c-hole and appropriate interval to be used for tracer tests.
Tracer Studies (Springer) This work is in support of tracer tests and must Le demonstrably related to intervals to be used for the tests. That relationship can be demonstrated by showing that the samples are from the depths and wells to be used for the tracer tests, or by showing mineralogy and chemistry of the samples and intervals to be tested are the same.
- 4) Identification by drill hole and depth Alteration History (Levy)
Requires samples identified by drill hole, stratigraphic unit (Independently verifiable) and depth to within 50 feet. S. Levy's comments follow:
"The most important product of Alteration History studies is not rock property data, but interpretations used to address issues concerning rates of geochemical processes in the geologic past, present, and future. The Alteration History studies are critically dependent on knowledge of spatial relationships among samples. Our interpretations of data from drill hole samples require drill hole location, stratigraphic position, and depth (a50 ft). We specifically require samples from a sufficient number of drill holes to provide the three-dimensional in formation necessary for interpretation of alteration history. The number of deep drill holes already in existence (UE25 ail, G-1, G-2, G-3, G-4, VH-1, VH-2, H-1, H-3, H-4, H-5, H-6) represents the bare minimum needed to provide acceptable support for our interpreta tions. .
If the existing drill hole samples and the data and interpretations based on study of the samples are found not to be acceptable for licensing, then certain statements on the favorability of Yucca Mountain already made in the Envi ronmental Assessment will be completely unsupported. A drilling program as ambitious as what has already been done would be required to replace the disqualified samples and provide equivalent evidence to support our interpretations. The concept of "corroborative data" - the idea that data from "disqualified" holes could be used to support conclusions based on data from future , acceptable holes -- is meaningless for our studies because the . characterization of unlocated samples has no value. l I believe that the body of documentation, taken all together, for each drill hole is sufficient to establish that the samples I have studied were correctly boxed and labeled as to drill core. With the use
t Attachment 2 Page 1 of 3 . Steve Leedom October 16, 1987 of drill core photographs and direct examination of drill core, it should be possible to determine, at an acceptable level of statistical certainty, that the core samples were accurately labeled." See you in November. Sincerely,_ JJ ' 4 .-. c- L >
- 8. Carlos Cy: CRM-4, MS A150 ESS-1, MS 0462
- 0. Vaniman,.ESS-1, MS 0462 J. Canepa, N-5, MS J521 P. Guthals, N-5, MS J521 L, Maassen, ESS-1, MS 0462
- 5. Levy, ESS-1, MS 0462 TWS Resident File, MS 0462 RPC File (G. Ortiz), MS J531 (2)
File G G G
1 l l l Attachmant 3 Page 1 of 1 Use of Existing Core for Licensing Most of the studies for geochemistry require that we characterize all units ! across the repository. block and along possible transport pathways to the accessible environment. Single key intervals used in these studies cannot be identified. We need all data obtained to develop a three dimensional model of Yucca Mountain. The studied do fall .nto two groups, however and these can be discussed separately.
- The least restrictive (in terms of core identification ) studies that we do are essentially generic. It is not necessary to independently identify the core or interval from which the sample came. The core is characterized using XRD, XRF and petrographic microcsope description of thin sections.
From this information it on be determined what unit, and of ten what lithologic interval within the statigraphic unit is present. The results are tied to lithology, mineralogy and chemistry. To demonstrate the appropriateness of the results to Yucca Mountain it need only be demonstrated that the lithology, mineralogy and chemistry of the samples used in these studies match the intervals of interest at Yucca Mountain. Samples can be taken f rom future drill core or the exploratory shaf t as appropriate to demonstrate this relationship. Studies that fall into this category are sorption studies and glass dehydration studies. For some of the sorption studies natural state samples have been used, and if those are accepted as QA Level-1 they will provide additional tie points to Yucca Mountain, but this should not be necessaary for acceptance of the data for licensing. The second category is the one that most Mineralogy-petrology studies fall l under. Waxed core has not been used in these investigations. Key samples l cannot be identified as it is necessary to characterize sorptive barriers along hydrologically transmissive zones across Yucca Mountain. Identification of the borehole from which the samples came is necessary. Vertical control to within +-50 feet is desired. If waxed core is accepted as QA Level 1, selected pieces could be analyzed to coroborate existing data for some activities, but probably would not be of much use for fracture mineralogy. many samples are examined and interpretations are based on a suite of samples rather than single occurrences. Misplacement of one or two samples would have no effect on results. Interpretations are tied to lithology and stratigraphy (independently determined) as well as depth. Data collected is internally consistent within stratigraphic intervals and between drill holes. Discussion of internal consistancy.is contained in the report by Broxton et al . (milestone T095, copy enclosed) . 1
PETROGRAPHY AND PHENOCRYST CHEMISTRY OF VOLCANIC UNITS AT YUCCA MOUNTAIN, NEVADA: A COMPARISON OF OUTCROP AND DRILL HOLE SAMPLES By D. E. Broxton, F. M. Byers, Jr., and R. G. Warren ABSTRACT This report is a compilation of petrographic and mineral chemical data for stratigraphic units at Yucca Mountain. It supports a possible peer retiew of Yucca Mountain drill core by summannng the available data in a form that allows comparison of stratigraphic units in drill holes with surface outcrops of the same units. These data can be used in conjunction with other geologic and geophysicalinformation to determine if stratigraphic relations in Yucca Mountain ddil core are geologically reasonable and compare well with relations known from extensive surface studics. Rock units at Yucca Mountain luve uniaue petrographic and mineral chemical characteristics that can be used to make accurate stratigraphic assignments in drill core samples. Stratigraphic units can be differentiated on the basis of petrographic characteristics such as total phenocryst abundances, relative proportions of phenocryst minerals, and types and abundances of mafic and accessory minerals. The mineral chemistry of phenocrysts is also an important means of differentiating among stratigraphic units, especially when used in conjunction with the petrographic data. Sanidine phenocrysts and plagioclase rims have narrow compositional ranges for most t units and often hav.e well defined dominant compositions. Biotite compositions are i useful for identifying groups of related units (e.g., Paintbrush Tuff members vs. Crater Flat Tuff members) and provide an important check on the consistency of the data. j Additional data should be collected to fully characterize units in drill holes and outcrops. However, the NNWSI Project should commit itself to the peer review ~ process as a means for qualifying the existing drill core before additional work of this type is undertaken.
I. INTRODUCTION In the summer of 1986, the Waste Management Project Office (WMPO) of the Nevada Nuclear Waste Storage Investigations (NNWSI) Project formed a Steering Committee to assess documentation supporting the traceability of core samples collected from drill hole USW G 4 at the Yucca Mountain site. This action was taken because of concem that much of the existing core collected for the NNWSI Project is not traceable as defined by Federal Regulation 10 CFR Pan 50, Appendix B. Lack of sample traceability could seriously restrict the use of existing core and of scientific tests conducted on this core as primary licensing data for a nuclear waste repository. The Steering Committee, made up of representatives from Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Sandia National Laboratories, Science Applications Intemational Corporation, the US Geological Survey and WMPO, submitted a final report and recommendations on October 26,1986. The Steering Committee report concludes that design and implementation of the quality assurance (QA) program in effect at the time the USW G-4 drill core was collected was inadequate to meet requirements of 10 CFR Part 50, Appendix B, and that documentation related to the drill core is inadequate to provide sample traceability. Funhermore, the Steering Committee concluded that drill core collected prior to USW G-4 also lacks adequate documentation for sample traceability. Although the documentation to support traceability was inadequate, the Steering Committee found no evidence that drill cores from Yucca Mountain were collected, transported, and stored in a manner that would compromise their integrity and warrant their exclusion from the licensing process. However, the lack of acceptable QA design, implementation, and documentation requires l thM the.se drill cores be qualified in some manner if they are to be used to support Quality Level I ( studies for the NNWSI Project. The Nuclear Regula'.ory Commission provides a mechanism for qualifying data that were not collected in conformance with an established QA program through the "Generic Technical Position on Peer Review for High Level Nuclear Waste Repositories". This position paper states that peer reviews may be employed as part of the QA actions'necessary
. ~c,.
to provide confidence in the adequacy of the data not collected in conformance with an established QA program. This report is a compilation of published and new modal petrographic data and phenocryst chemistry data for stratigraphic units at Yucca Mountain. 'ntis compilation is made to support peer review activities by summarizing the available petrographic and mineral chemistry data in a fann that allows a comparison of stratigraphic units in drill holes with surface outcrops of the same 2
units. Peer reviewers can use these data in conjunction with other geologic and geophysical information to determine if geologic relations determined by drill cor:s at Yucca Mountain are reasonable and compare well with relations known from extensive study of surface exposures by the U.S. Geological Survey in connection with the nuclear weapons testing program. The drill holes considered in this report include USW G 1, USW 0 2, USW GU 3, USW G 3, USW G-4, UE 25a#1, UE 25b#1H, UE-25p#1, and J-13. The locations of these drill holes are shown in Fig. 1. IL GEOLOGIC SETTING Yucc- Mountain is located south of the Timber Mountain Oasis Valley caldera complex in the southwest Nevada volcanic field (Byers et al.,1976a and 1976b: Christiansen et al.,' 1977). Yucca Mountain is an east-tilted fault b$ck uplift underlain by at least 1.8 km of silicic volcanic '
~
i rocks. Table Ilists the major stratigraphic units at Yucca Mountain. These volcanic units wbe erupted from the Timber Mountain-Oasis Valley caldera complex (Byers et al.,1976b; Christiansen et al.,1977) between 9 and 16 my ago (Kistler,1968 and Marvin et al.,1970; corrected using new constants in Dalrymple,1979). Most units consist of compositionally homogenous rhyolitic ash-flow and ash fall tuffs. However, the Topopah Spring and Tiva Canyon Members of the Paintbrush Tuff are large volume compositionally zoned ash-flow sheets that grade up in section from high-silica rhyolite to quartz latite. Relatively small bodies of dacitic lavas and flow breccias were penetrated below the Crater Flat Tuff by drill holes USW G-1 (Spengler et al.,1981) and USW G 2 (Maldonado and Koether,1983)in the northem part of l Yucca Mountain. Stratigraphic relations within the volcanic field are summarized by Byers et al. (1976b) and by W. J. Carr et al. (1986). Most of the volcanic field was mapped at a scale of l 1:24,000 and a map of the Timber Mountain Oasis Valley caldera complex has been compiled at a ~ scale of 1:48,000 (Byers et al.,1976a). ~
~
1
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IH. METHODS Petrographic and mineral chemical data for the stratigraphic units at Yucca Mountain were l compiled from published US Geological Survey and Los Alamos National Laboratory report:. Petrographic data for 416 samples were compiled from Lipman et al. (1966), Quinlivan and Byers (1977), Sykes et al. (1979), Byers and Warren (1983), Warren et al. (1984), Scott and Castellanos (1984), Byers (1985), and Byers and Moore (1987). The reader is referred to these reports for a l l 1 l
l l l l l description of their methods. This report also contains 105 new modal analyses obtained by the i authors. We used standard point counts employing both transmitted and reflected light microscope techniques to determine phenocryst volume percents. Between 500 and 5000 counts i per sample were made to determine the abundances of phenocrysts, lithic fragments, and voids in thin sections. One of us (RGW) determined the abundances of accessory minerals in samples that he analyzed. The method for detemunmg accessory mineral abundances is described in Warren et al. (1984). Briefly, thin sections are systematically searched in transmitted and reflected light for accessory minerals. Once located, the positions of these minerals are plotted on a 11" X 14" black and white negative photograph image of the thin section. The photograph serves as a record of where each mineral is located and prevents duplicate measurement of individual minerals. Using a calibrated grid mounted in the microscope eyepiece, the surface area of each accessory mineral is measured in reflected light. Identifications are aided by qualitative microprobe analysis where uncertain. The concentration of each accessory mineral is the areal sum of all measured grains divided by the thin section area. Microprobe data presented in this report includes our unpublished data and published data from Sykes et al. (1979), Broxton et al. (1982), and Warren et al. (1984). The data we present includes the onhoclase and celsian (Or + Cn) component of sanidine, the anorthite (An) compenent of plagioclase, and Mg* [Mg!(Mg + Fe) x 100) in biotite. Other mineral chemical data such as Ba in feldspars and biotite and Tiin biotite can also be used to characterize stratigraphic units but are not discussed in this report. Chemical compositions of phenocrysts were determined by wave-length dispersive X ray analysis with an automated Cameca electron microprobe oper red a: 15 kev and a 15- to 20-nA beam current. Procedures, standards, and analytical uncertainties for microprobe analysis are described in Warren et al. (1984). No attempt was made to tabulate the existing microprobe data in this repon because of the large number of analyses that have been performed for these rocks. These data are summarized graphically to facilitate comparisons between drill hole and outcrop samples as well as comparisons among drill hole samples. IV. RESULTS Table II contains the petrographic data for the stratigraphic units at Yucca Mountain. These data are sununarized for each unit as histograms of total phenocryst abundances and as triangular plots showing proponions of quanz, sanidine, and plagioclase phenocrysts. Additional figures 4
contain histograms showing the range and dominant compositions of sanidine. plagioclase, and biotite for each unit. Data for outcrop and drill hole samples are presented separately in all figures to facilitate comparisons between these different sample types. V. DISCUSSION The following discussion describes the major stratigraphic units at Yucca Mountain it. order of ascending stratigraphic position. Each description includes a brief overview of unit lithology, unit distribution in outcrop and in drill hole, and available data sources. Next, the characteristic petrographic and mineral chemical properties of the unit are discussed and features that distingutsn the unit from others are described. Finally, comparisons are made for drill hole vs. outcrop da:a and for data collected among the various drill holes. These comparisons are of a preliminary nature because evaluation of the' data for the parpose of qualifying the core is the responsibility of a peer review pcnel. A. Older Volcanic Units Tbc oldest volcanic units at Yucca Mountain are bedded and ash-flow tuffs and quanz latitic to rhyolitic lavas and flow brsccias penetrated near the bottoms of drill holes UE 25p#1, USW G-1, USW G 2, and G 3. Stratigraphic correlations among these lowermost volcanic units are uncertain except for a sequence of non- to moderately welded ash flow tuffs and lavas informally designated in ascending order as units C, B, and A (Spengler et al.,1981; Scott and Castellanos, 1984). Units C, B, and A are individual cooling units separated by bedded tuffs. 'Ihey are thought to crop out in the Bullfrog Hills west of the Timber Mountain Oasis Valley caldera complex (Maldonado, personal communication,1985), but thus far no detailed petrographic work has been done on these possible sudace equivalents. Unit C may be stratigraphically equivalent to the biotite hornblende rhyr>1ite west of Split Ridge on Pahute Masa; both units are similar in petrography and mineral, chemistry and occur at similar stratigraphic positions within the volcaniE section Units C overlies the tuff of Yucca Flat in drill ho?e UE 25p#1 (M. D. Carr et al.,1986).
- 1. Older Tuffs Unit C. Petrographic and mineral chemical data for Unit C are presented for drill holes USW G 1 (Warren et al.,1984), USW G-2 (Broxton et al.,1982; and this repon), and UE 25p#1 (this report) in Table II and in Figs. 2 and 3. Although data from equivalent outcrops cannot be included in this comparison because equivalent outcrops are uncenain or unknown, the data from the three drill holes can be examined for intemal consistency within a drill hole as well as for consistency between drill holes.
5 s .
Unit C is a plagioclase. rich ruff that contains 6 to 27% phenocrya (Fig. 2a). Quartz and sanidine typically make up less than 15% of the felsic phenocrysts (Fig. 2b). Mafic phenocrysts consist of biotite, hornblende, and clinopyroxene in order of decreasing abundance (Table II). Accessory minerals include Fe Ti oxides, apante, allanite, sphene, zircon, and perrierite (Table II). Despite pervasive diagenetic alteration, most feldspar phenocrysts in these rocks retain their original maginatic compositions (Warren et al.,1984). Sanidine compositions are relatively potassic in Unit C (Or70-74; Fig. 2c) compared to most overlying units. Plagioclase compositions range from An26 ot An46. Biotites are magnesium r.ch with compositions averaging about Mg*62 (Fig. 2c). Unit C has similar phenocryst and accessory mineral assemblages in the three drill holes which penetrsted this unit (Table II). Total phenocryst contents are unusually variable for this unit (Fig. 2a), but tids variability may reflect winnowing of glassy pyroclasts or physical sorting of phenocrysts during emplacement of these tuffs. Felsic phenocryst proportion! and mineral compositions, which are v.affected V such processes, are similar f.,r drill holes USW G-1 and l'SW G-2 (Figs. 2b and 2c).
- 2. Older Tuffs Unit B. Modal petrographic data for Unit B are available cnly for drill hole USW G 1 (Warren et al.,1984). Phenocryst compositions are also limited to two samples from USW G-1 (Warren et al.,1984). These data are summarized in Table II and in Fig. 2.
Unit B contains 10 to ? 8% phenocrysts (Fig. 2a) consisting of plagioclase, sanidine and quartz. Tog.ther, sanidine and quarta make up about 40% of the felsic phenocryst phases (Fig. 2b). Biotite is the only major matic phenocryn phase. Accessory minerals incluh Fe-Ti oxides, apatite, ananite, sphene, zircon, crd petrierite (Table II). Most sanidine phenocrysts have compositic s ranging between Or66 70 (Fig. 2c). I Plagioclase compositions appear to be bimodal :h modes clustering around An23 and An30 (Fig. 2c). Plagicclare compesitions clusterint; aroui._ An30 may represent xenoctysts picked up from i the underlying plagioclase-deb Unit C or may reflect the dominant compositians of calcie cores in noned plagioclase crystals. Biotite corr ositions are magnesium rich (Mg*59; Fig. 2c). l ^ 't B is distinguished from Uait C by a higher proportion of sanidine and quartz as ~ ic
- r. r a ', Fig. 2a) and by more sodic sanidine compositions (Fig. 2c). If the plagioclase_.
e s clustering near.t139 are xenocrystic, then plagioclase compositions representing
- r- .41ues for Unit B are also more sodic than those in Unit C. Existing modal and mineral l
l f 6 l l l . I
~ 1 l
l l chemical data are too sparse to assess the intemal consistency of petrochemical characteristics in I , Unit B.
- 3. Older Tuff Unit A. Modal petrographic data for Unit A of the older tuffs are reponed for USW G-1 (Warren et al.,1984), USW G 3 (this report), and UE 25p#1 (this report).
Mkroprow data for plagioclase, sanidine, and biotite ne presented in Warren et al. (1984). Rese data are summarized in Table II and in Fig. 2. Unit A contains 8 to 247c phenocrysts (Fig. 2a) consisting predominant 4y of plagioclase, sanidine, and quartz. Sanidine and quanz make up 55 to 70ro of the felsic phenocrysts (Fig. 2b). Biotite and trace amounts of homblende are the mafic phenocrysts (Table II). Accessory minerals consist of Fe-Ti oxides, apatite, allanite, sphene, and zircon (Table II). Sanidir.e compositions in Unit A are more sodic (mostly Or62-68) than those in Units B or C (Fig. 2c). Plagioclase compositions are bimcdal with modes clustering around An19 and An30-' Plagioclase rim compositions range from Anl440. Plagioclase compositions cluste' ring'around An30 are similar to those found in Units B and C and represent core and midzone compositions in chemically zoned crystals. Siotite compositions, which cluster around Mg*55, am more iron rich than those in Units B and C (Fig. 2c). The modal data for Unit A are consisten: for drill holes USW G-1, USW G 3, and UE-25p#1. Total phenocryst contents C:ig. 2a), reiative proportions of felsic phenocrysts (Fig. 2b), and accessory mineral assemblages (Table IIj overlap among the three drill holes. Mineral chemical data are available only for USW G-1; of these data sanidine and biotite compositions have narrow compositional ranges and together with the modal data show intemal consistency within the drill hole (Table II). In a broader comparison, each of these older units is clearly distinguishable from one another. Going upsection, each unit becomes systematically richer in sanidine and quartz (Fig. 2b), has more sodic sanidine and plagioclase compositions (Fig. 2c), and has more iron rich bintites (Fig. 2c). '~ B. Lith _ic, Ridge Tuff Mcdal petrographic data for the Lithic Ridge Tuff were compiled from Wanen et al. (1984) for drill holes USW G-1 and J 13, from Byers and Warren (1983) for drill hole J-13, and from Scott and Castellanos (1984) for drill hole USW G 3. New modal analyses are also presented for I drill holes USW G 2, J 13, and UE 25p#1 as well as for three outcrop samples. Modal data for - outcrop samples were taken from Quintivan and Byers (1977) and Warren et al. (1985). Microprobe analyses of phenocrysts were compild for driU holes USW G-1, USW G 2, and J-13 7
from Warren et al. (1984) and Broxton et al. (1982). nese dr.:a are summarized in Table II an Fig. 3. The 1.ithic Ridge Tuffis a quanz. poor unit that typically contains about 10% phenocrysts (Fig. 3a). Plagioclase predominates over sanidine (Fig. 3b), and biotite is the major mafic phenocry.<t phase. Small amounts of homblende occur in a few samples. Accessory minerals include Fe Ti oxides, sphene, a11anite, apatite, and urcon (Table II). Lithic fragments of pilotaxitic lavas and welded tuff are abundant throughout the unit commonly makmg up 10-40?c of the rock (Table II). The persistence of high lithic fragment contents throughout the Lithic Ridge Tuff make it an exc::11ent marker bed (W. J. Cyr et al.,1986). Sanidine compositions cluster between Or62 and Or68 (Fig. 3c) and thus m similar to those of Unit A. Plagioclase core compositions are widely scanered, falling primarily between Ant 4 a An50. Plagioclase rims define a narrower compositional range occurnng mostly between An16 2 (Fig. 3c). Biotite compositions ne relati ely magnesium rich, ranging in composition between i Mg*54 70 and concentrating arot.nd Mg*59 (Fig. 3c). The four outcrop samples of the Lithic Ridge Tuff are slightly less phenocryst rich than most drill core samples, owing to less dense welding (compaction); however, the phenocryst abundances of the outcrop samples overlap the lower end of the range observed in drill holes (Fig. 3a). The proponions of felsic phenocrysts in the outcrop samples are similar tt. those in d:ill core samples
.tnd the assemblage of mafic and accessory phases is the same (Fig. 3b: Table II). Compositions of sanidine phenoctysu match well when dnll core samples are compared to the one outcrop sample that was analyzed (Fig. 3ch Plagioclase and biotite compositions do not form as tight a compositional group as the sanidines, bm i is clear from Fig. 3c that the compositional :anges for these minerals in outcrop and drill core overlap. In addition to a generally favorable comparison between drill hole and outcrop data, there is good agreement among the various drill holes when the modal and mineral chemical data are compared (Figs. 3a, b, and c). One exception is the high -
Mg biotite (Mg*70) reported in one sample (U5W G2-4199); the biotite in this sample is substantially more magnesium rich than other sample: for this unit (Fig. 3c). ' This sample is the stratigraphically highest sample of Lithic Ridge Tuffin USW G-2. It contains no sanidine and quanz, has Ca rich plagioclase, and has >1?c homblende. This sample may represent ash flows that tapped deeper, more mafic levels of the Lithic Ridg magma chamber. Dacitic lava flows and flow breccias overlie the Lithic Ridge Tuffin the sulaface in the northem pan of Yucca Mountain. These dacitic rocks were penetrated in drill holes USW G-2 and 8 m
I USW G 1. Moda! data fo? these intermediate composition rocks are presented in Table C, but are not discussed further in this repon. Mineral chemical data for these ro:ks are presented in Warren et al. (1984). , C. Crater Flat Tuff The Crater Flat Tuff comprises three ash flow tuff cooling units. In ascending order these are the Tram, Bullfrog, and Prow Pass Members (Table I). These three ash flow sheets are rhyolitic in composition and crop out south and east of the Timber Mountain Oasis Valley :aldera complex: tuffs and lavas with similar petrochemical characteristics occur ta the same stratigraphic interval in the subsurface at the Silent Canyon caldera to the north (Warren,1983). At Yucca Mountain, the Crater Flat Tuff overlies dacitic lavas and flow breccias in the northern part of Yucca Mountain and the Lithic Ridge Tuff in the southem part. The Bullfrog Member has a K/Ar age of 13.9 Ma (Marvin et al.,1970; W. J. Carr et al.,1986).
~
- 1. Tram Member. Modal data for the Tram Member were cc,mpiled from Byers and Wanen (1983) for samples from J-13, from Scott and Castellanos (1984) for samples from USW G 3, and from Warren et al. (1984) for outcrop samples and samples from USW G 1 and J.
- 13. In addition, new modal data are presented for one outcrop sample and for samples from dr21 holes UE 25p#1, USW G 2, and USW G.4 in Table 'I and Fig. 4a ard 4b. Microprobe analyses of phenocrysts (Fig. 4c) were compiled for drill holes USW G.1, USW G.2, UE 25b#1H, UE.25p#1 and J 13 from Wanen et al. (1984), Broxton et al. (1982), and M. D. Carr et al. (1986). Additional unpublished microprobe data for feldspar phenocrysts in one outcrop sample and for two samples from UE-25p#1 are also presented in Fig. 4c.
The Tram Membet comrnonly contains between 6 and 16% phenocrysts (Fig. 4a) consisting primarily of subequal amounts of quanz, sanidine, and plagioclase (Fig. 4a). Mafic phenocrysts include biotite and trace amounts of homblende. Act.essory rainerals consist of Fe Ti oxides, apatite, allanite, and zircon (Table II). Higher quartz contents and lack of sphene readily distinguish the Tram Member from the underlying Lithic Ridg: Tuff. Also, the Tram Member is I generally lithic rich only in its loer part (e.g., USW G-1 and USW G 3 (Table U), wheren the Lithic Ridge Tuff is lithic rieb throughout. Sanidine compositions cluster around Or67 and plagioclas' core compositions fall primarily between An16 and An40 (Fig. 4c). Plagioclase rims have compositions mostly between Antg.24 The compositions ofinese feldspr phenocrysts are similar to those found in the Lithic Ridge Tuff (Fig. 3c). Biotite phenocrysts in the Tram Member, on the other hand, are distinctly more iron rich
(Mg*34-52) than those in the Lithic Ridge Tuff (Mg*S4-70). The few magnesium rich biotites found in the Trarn Member (Fig. 4c) are probably xenocrysts from underlying units. There is good agreement between the drill hole samples and the outcrop samples when the petrographic and mineral chemistry data are compared. The phenocryst and accessory mineral assemblages are similar for samples from drill hole ad from outcrop. The mineral chemistry of phenocrysts also matches well, panicularly for sanidine and biotite. Modal and mineral chemical data also compare wen among the drill holes for which data are available.
- 2. Bullfrom Member. Modal petrographic data for the Bullfrog Member were compiled from Quinlivan and Byers (1977) for outcrop samples, from Byers and Warren (1983) for samples from J-13, from Scott and Castellanos (1984) for samples from USW G-3, and from Warren et al.
(1984) for outcrap samples and samples from USW G-1, J 13 and UE 25a#1. In addition, new modal data are presented for samples from drill holes USW G 2 and USW G 4 in Table II. Microprobe analyses of phenocrysts were compiled for diill holes USW G 1, USW G-2, UE-25a#1, UE 25b#1H, aid L13 from Warren et at (1984), Bre tton et al. (1982), and Sykes et al. (1979). New feldspar compositional data are presented for one sample from UE-25p#1. The Bullfrog Member commonly contams between 8 and 209c phenocrysts (Fig. Sa) consisting pnmanly of plagioclase, sanidine, and quanz in order of decreasing abundance (Fig. Sb). The mafic phenocrysts are biotite, homblende, and trace clinopyroxene (Table II). Accessory minerals consist of Fe Ti oxides, apatite, allanite, and zircon. Lower qt.artz contents, wormy quanz, and relatively abundant homblende readily distinquish tne Bullfrog Member from the underlying Tram Member. In addition, the Bullfrog Member as generally lithic poor throughout tyhereas the Tram Member has a lithic rich base in the vicinity of Yucca Mountain. Sanidine compositions in the Bullfrog Member are dominately Or60 64 and plagioclase core compositions fall primarily between An10 and An40 (Fig. Sc). Plagioclase rim compositions cluster from An10-18. B.oth plagioclase and sanidine tend to have more sodic compositions than i 1 those found in the Tram Member. Biotite compositions in the Bullfrog Memoer panially overlap those of the Tram Member, but generally are slightly more iron rich (~Mg*40)- l Phenocryst abundances of outcrop samples overlap those of drill hole samples for the Bullfrog Member (Fig. Sa). The proportions of felsic phenocrysts in the outcrop samples agree well with those in drill core samples and the assemblage of mafic and accessory phases is the same f (Table II). The Bullfrog Member is characterized by sanidines that define the same narrow compositional range in outcrop and in drill core (Fig. Sc). Plagioclase and biotite compositions do l 10 l
l l 1 not form as tight a compositional group as the sanidines, but the compositional ranges for these minerals in outcrop and drill core overlap. Plagioclase rims, on the other hand, have distinct sodium rich compositions in both outcrop and drill holes; these sodic plagioclase rims distinguish the Bullfrog Member from underlying units. Like the comparison between drill hole and outcrop data, there is good agreement among the various drill holes when the modal and mineral chemical data are compared (Figs. Sa, b, and c).
- 3. Prow Pass Member. Modal data for the Prow Pass Member were compiled from -
Quinlivan and Byers (1977) for outcrop samples, from Byers and Warren (1983) for samples from J-13, from Scott and Castellanos (1984) for samples from USW G 3, and from Warren et al. (1984) for outcrop samples and samples from USW G-1, J-13, and UE 25a#1. In addition, new modal data are presented for samples from dnll holes USW G 2 and USW G-4 in Table II. Microprobe analyses of phenocrysts were ce= pled for drill holes USW G 1, USW G 2, UE 25a#1, and J-13 from Warren et al. (1984), Broxton et al. (1982), and Sykes et al. (1979). New dau hr sanidine compositions are prescraed for UE-25p#1. A few of the quartz rich samples of the Prow Pass Member from northem Crater Flat analyzed by Quinlivan and Byers may actually be samples of the altered Bullfrog Member. The Prow Pass Member generally contains 6 to 149c phenocrysts (Fig. 6a) consisting pnmarily of p'agioclase, sanidine, and quartz. The Prow Pass Member contains slightly less quanz (Fig. 6b) thzn the lower members of the Crater Flat Tuff (Figs. 4b and Sb); characteristically, this quartz is extremely embayed and wormy. Mafic phenocrysts are biotite, hornblende, and orthopyroxene (Table II). ne presence of Fe rich orthopyroxene is useful in identifying the Prow i l Pass Member because it is found only in this unit at Yucca Mountain. The accessory mineral assemblage of the Prow Pass Member consists of Fe Ti oxides, apatite, allanite, and zircon (Table g), . - . - Feldspar phenocryst compositions in the Prow Pass Member are more sodic than those of the
~'
two lower members of the Crater Flat Tuff (Figs. 4c, Sc,'and 6c). he compositions of sanidne phenocrysts are dominately Or50-56. Plagioclase compositions concentrate between An8 and Ang4, though crystals with more calcie midzones and cores are found in a few samples. Plagioclase rim compositions are dominately A- 12. There are relatively few analyses of biotite phenocrysts for the Prow Pass Member (Fig. 6w. Most of the available biotite compositions fall between Mg*38-54 and thus overlap those of the two older members of the formation. i l l 11 L -
Outcrop data for the Prow Pass Member are sparse, consisting of modal analyses for four samples and mineral chemical da a for two samples. Agreement between the data sets for outcrop and drill hole samples is generally good, but additional work should be conducted on outcrop samples to better establish 'his relationship. Phenocryst abundances in the four outcrop samples overlap the upper end of the range observed in drill holes (Fig. 6a). The proportions of felsic phenocrysts in the outcrop samples are similar to those in drill core samples (Fig. 6b) with the possible exception of two quartz rich samples, which may be Bullfrog. The assemblaget of mafic and accessory phases ne the same (Table II). Compositions of sanidine and plagioclase phenocrysts match well when drill core samples are compared to the two outcrop samples that were analyzed (Fig. 6c). Biotite compositions are sparse for both drill holes and outcrops; however, there is overlap between the two data sets for the available analyses (Fig. 6c). There is good agreement among the various drill holes when the modal and mineral chemical data are compared (Figs. 6a, b, amd c). Feldspars in panicular have distinct compositional signatures that are found in ali of the drill hole samples analyzed. Although there is considerable scatter in modal data, owing to possible misidentified outcrops, there is generally a good correspondence between data from different drill holes. Two of the three samples from J 13 are somewhat more crystal rich than samples from other drill holes. The proportions of felsic phenocrysts are known in only one of these two samples; these felsic phenocryst proportions are similar to those found in other samples of the Prow Pass Member. D. Tuffaceous Beds of Calico Hills The tuffaccous beds of Calico Hills are a sequence of ash flow and ash fall tuff, volcaniclastic sediment, and rhyolitic lavas. At Yucca Mountain, the unit consists primarily of numerous nonwelded ash-flow tuffs which in places are separated by thin ash-fall and reworked tuffs. The Calico Hills unit thins southward frorn 289 m at USW G-2 (Maldonado and Koether, i I 1983) to about 29 m in USW GU 3 (Scott and Castellanos,19S3). The tuffaceous beds of Calico l Hills have been dated at 13.8 Ma by K-Ar methods (Marvin et al.,1970: using the new constants in Dalrymple,1979). Modal data for the tuffaceous beds of Calico Hills were compiled from Warren et al. (1984) l for samples from USW G 1 and from Scott and Castellanos (1983) for samples from USW GU 3. l New modal data az ' presented for samples from drill holes USW G 2, USW GU 3, and USW G-4 and for outcrops of tuffs north of Yucca Mountain and lavas in Paintbrush Canyon. Microprobe l 12 1 5
analyses of phenocrysts were compiled for drill holes USW G 1 (Warren et al.,1984) and USW G 2 (Broxton et al.,1982). New microprobe data are presented for three outcrop samples. The Calico Hills unit is generally phenocryst poor (< 4% crystals) at Yucca Mountain (Fig. 7a). However, the lower part of the unit is phenocryst rich (up to 25% crystals)in drill holes USW G-1 and USW G 2 as well as in outcrop north of Prow Pass (Fig. 7a). Phenocrysts consist of plagioclase, sanidine, and quartz (Fig. 7b) and minor amounts of biotite (Table H). Homblende, clinopyroxene, and onhopyroxene occur in trace amounts in a few samples. Quartz is commonly wormy, but this texture is not as well developed as in the Bullfrog and Prow Pass Members. Accessory minerals include Fe Ti oxides, allanite, apatite, and zircon (Table H). The compositions of sanidine phenocrysts are dominately Or66 74 (Fig. 7c). Sanidine compositions in the lower phenocryst rich subunits are slightly more potassic (Or70-74) than those in the phenocryst poor rocks (Or66 70); these subunits are not subdivided in Fig. 7c, except for outcrop samples, which are all from the lower phenocryst rich subunit. Most plagioclase compositions concentrate between Ang4 and An30. The dominant plagioclase rim compositions are An20 for P henocryst poor rocks and An25 for P henocryst-rich rocks. Analyses of biotite phenocrysts are published for drill holes USW G 1 and USW G 2. These biotites have compositions ranging between Mg*34 50: biotites in outcrop samples have not been analyzed yet. Comparison of outcrop and drill hole data is complicated by the vertical tineralogic and mineral chemical gradients in the tuffaceous beds of Calico Hills. The comparison of modal data is also made difficult by scatter in the proportions of felsic phenocrysts, particularly for phenocryst poor samples (Fig. 7b). 'Dtis scatter is due to the crystal poor nature of the unit which results in poor counting statistics and in gross inhomogeneities in phenocryst assemblages at the thin-section scale. Nevertheless, the lower crystal contents in the upper part of the unit and the highe, proportion of que.rtz phenocrysts throughout clearly distinguish the tuffaccous beds of l Calico Hills from the underlying Prow Pass Member. The available data for feldspar compositions t ,
, .- u. ..
l for outcrop samples mostly represent the lower phenocryst rich subunit whereas the drill hole data include both phenocryst poor and phenocryst rich rocks. These feldspar compositions clearly
- distinguish the Calico Hills unit from the Prow Pass Member, which has significantly more sodic l feldspars (Figs. 6c and 7c).
E. Paintbrush Tuff - The Paintbrush Tuffis composed of four ash flow tuff cooling 'mits consisting of,in ascending order, the Topopah Spring, Pah Canyon, Yucca Mountain, and Tiva Canyon Members 13
(Table I). The Topopah Spring and Tiva Canyon Members are large volume compositionally zoned ash flow tuffs which crop out east and south of the Timber Mountain Oasis Valley caldera complex. These units also occur in the subsurface north of the caldera complex. The caldera source for the Topopah Spring Member was buried by younger calderas related to the Timber Mountain Tuffs (Byers et al.,1976b). The Tiva Canyon Member was erupted from the Claim Canyon caldera, a small segment of which is preserved north of Yucca Mountain (Byers et al., 1976b). 'Ihe Pah Canyon and Yucca Mountain Members are relatively sma'l rhyolitic ash flow tuff cooling units exposed south of the Timber Mountain Oasis Valley caldera complex. At Yucca Mountain these uniu thin southward away from their source areas in the caldera complex and are absent in drill boles south of UE 25a#1. Bedded and nonwelded ash flow tuffs are locally present between the members of the Paintbrush Tuff at Yucca Mountain; lavas are intercalated in the Paintbrush Tuff north of Yucca Mountain and in Yucca Wash. The Topopah Spring Member has a K/Ar age of 13.4 Ma (Kistler,1968; Marvin et al.,1970). The age of the Tiva Canyon Member is 12.9 Ma (Kistler,1968; Marvin et al.,1970).
- 1. Topopah Spring Member. Modal data for the Topopah Spring Member were compiled from Lipman et al. (1966) for outcrop samples; from Byers (1985) for USW G-4; from Byers and Moore (1987) for USW G 1, USW G 2, USW GU 3, and UE 25a#1; from Scott and Castellanos (1984) for samples from USW GU-3; and from Wanen et al. (1984) for samples from USW G 1.
In addition, new modal data are presented for outcrop samples and for samples from drill holes J-13, UE 25a#1, and UE 25p*1 in Table II. Microprobe analyses of phenocrysts were compiled for drill hole USW G 1 from Warren et al. (1984) and for USW G-2 from Broxton et al. (1982). New microprobe data for phenocryst compositions are presented for samples from UE 25a#1, J 13, USW G-4, and UE 25p#1 as well as for outcrop samples. At Yucca Mouritain the Topopah Spring Member is about 300 m thick. About 250 m in the lower part of the unit consists of compositionally homogenous, crystal poor, high silica rhyolite; this rhye.Me grades abruptly upward into a 50 m caprock of crystal-rich quanz latite. Data for these compositionally distinct zones are presented separa:ely in Fig. 8. Phenocrysts make up less than 2% of the rock in the rhyolitic pan of the memb:r and make up 5 20% of the rock in the quartz latitic part (Fig. Sa). Modal data for the rhyolitic ponion of the member are characterized by considerable scatter because of its crystal poor nature (Fig. 8b).
~
Plagirelase and sanidine are the principal felsic phenocrysts with plagioclase being the more abundant felsic phase in most samples of rhyolite, whereas sanidine is more abundant in the quartz 14
latite (Fig. 8b). Sanidine occurs as freestanding phenocrysts in the rhyolite and quartz ladte; it also occurs as mantles uound plagieclase phenocrysts in the quanz latite. Quartz is found in small amounts in the rhyolite and mostly occurs near the base of the unit. Quartz is ruely found in samples of quartz ladte. Mafie phenocysts in the rhyolite consist of biotite and of trace amounts of clinopyroxene and homblende (Table II). He quartz latite contains biotite, clinopyroxene, and trace homblende (Table II). ne member contains Fe Ti =S:, spatite. and zircon as accessory minerals. In addition, the rhyolite contains allanite as the common rare earth bearing phase, whereas the quanz latite contains perrierite (Table II). Sanidine compositions in the Topopah Spring Member are characterized by a relatively ; broad range in compositions compared to most underlying units (Figs. Oc and 8d). Sanidine compositions of the rhyolites and quartz latites concentrate primarily between Or38 and Or66. The , ranges in sar.idine compositions overlap between the rhyolite and the quanz latite: however, sanidine is typically more potassie in the rhyolite. Within the rhyolite, sanidine compositions become increasingly potassic towards the base of the unit. Plagioclase phenocrysts also have a wide range of compositions in the Topopah Spring Member. Most compositions in the rhyolite fall between Ang4 and An20 with the dominant composition occurring at Ani7. A minor compositional mode occurs at An35. Plagioclase in the quanz latite also appears to be bimodal with major modes occurring at An17 and An26. Biotite compositions are relatively iron rich (primarily Mg*34-50) in the rhyolite compared to the quatz latite (primarily Mg*60 66)- In rhyolitic samples, the proportions of felsic phenocrysts are similar for outcrop and drill hole sampl:s (Fig. 8b). Phenocyst contents are consistently less than 2% in samples from both drill holes and outcrop (Fig. Sa). Sanidine and biotite compositions in the rhyolitic pan of the member agree well when comparisons ne made between drill holes (Fig. Sc), but compositional data are lacking for a comparison of d:ill hole and outcrop samples. Nonwelded rhyolitic tuffs near the base of the member c' an be distinguished from the' underlying tuffaceous beds of Calico Hills by lower quanz contents (Figs. 7a and 8b) and by generally more 'sodic feldspar compositions in the Topopah Spring Member. In the quarte latitic samples, modal and mineral chemical l characteristics for outcrop and drill hole samples ste similar (Fig. Sa, b and d). The quanz poor, l l sanidine rich petrography of the Topopah Spring quartz latite distinguishes it from all underlying l units. De compositional fields and dominant .:ompositions for feldspar and biotite phenocrysts in the quartz latite are similar for outcrop and drill holes (Fig. 8d). l . 15 ( ' l I
2dah Canvon Member. Published modal and mineral chemical data for the Pah Canyon Member are sparse. Modal analyses for four outcrop samples wer, compiled from Quinlivan and Byers (1977). Eight new modal analyses are presented for &ill holes USW G-2 and UE 25t.#1. At present there are no microprobe analyses of phenocrysts from outcrop samples. Broxton et al. (1982) present mineral chemical data for the Pah Canyon Member in drill hole USW G 2. New mineral chemical data for one sample from UE 25a#1 are presented in this paper. The Pah Canyon Member contains 4 to 129o phenocrysts (Fig. 9a) consisting primarily of subequal amounts of plagioclase and sanidine (Fig. 96). Sanidine occurs both as freestanding phenocysts and as mantles around plagioclase phenocrysts. Biotite and clinopyroxene comprise the mane phenocryst assemblage (Table II). Like other members of the Paintbrush Tuff, the Pah Canyon Member contains only trace amounts of quanz. Accessory minerals consist of Fe Ti oxides, apatite, perrierite, sphene, and zircon (Table H). The petrography of the Pah Canyon Member is very similar to that of the quaru latite in the Topopah Spring Member. Except for the presence of sphene in the Pah Canyon Member, the two units have similar phenocryst assemblages. However,in ten of the twelve samples for which data are available the Pah Canyon has a greater proportion of plagioclase phenocrysts than does the Topopah Spring quartz latite. Phenocryst compositions in the Pah Canyon Member are also very similar to those found in the Topopah Spring quartz latite. Sanidine compositions range from Or46-60 with a dominant mode at Or52 54 (Fig. 9c). Plagioclase compositions concentrate between Ang4 and An;2 though crystals with more calcie midzones and cores are found in a few samples. Biotite phenocrysts detine a narrow compositional range (Mg*58-68) with most analyses oceumng between Mg*62-68 (Fig. 9c). The modal data for drill hole and outcrop samples compare favorably. Phenocryst abundances and modal proportions overlap between the two data sets (Fig. 9a and b). Compositions of sanidine and plagioclase phenocrysts also match well for samples in the two drill holes analyzed (Fig. 9c); however, there are no n.ineral-chemical data for any outcrop samples for comparison. Biotite compositions also match well for the samples in the two drill holes (Fig. 9c).
- 3. Yucca Mountain Member. ne Yucca Mountain Member is a shard rich ash flow tuff that is essentially phenocryst f ee (<0.19e crystals). The rare phenocrysts occurring in this unit include sanidine, plagioclase, and biotite nese phenocrysts are much smaller (<0.3 mm) than phenocrysts typically found in other units at Yucca Mountain. The paucity of phenocrysts, the shard rich nature of the matrix, and the presence of diagnostic grayish red lithics less than 1 cm in 16
diameter clearly distinguish the Yucca Mountain Member from other stratigraphic units at Yucca Mountain. Because ofits nearly phenocryst free character, no modal analyses are published for the Yucca Mountain Member. One new modal analysis of an outcrop sample is given in Table II. Mineral compositions for feldspar and biotite phenocrysts were published in Broxton et al. (1982); these data are summanzed in Fig.10,
- 4. Tiva Canyon Member. The Tiva Canyon Memberis the youngest volcanic unit in the exploration block. Modal data for the Tiva Canyon Member were compiled from Quinlivan and Byers (1977) for ten outcrop samples and from Scott and Castellanos (1984) for six samples from USW GU 3. In addition, new modal data are presented for three outcrop samples, one sample from J-13, three samples from UE-25a#1, and three samples from UE.25p#1 in Table II. New micropmbe data for phenocryst compositions are presented for one sample from J-13 and for two outemp samples.
The Tiva Canyon Member is a compositionally zoned unit which grades'up in section from l rhyolite to quartz latite. Like the Topopah Spring Member, the lower part of the Tiva Canyon Member consists of crystal poor, high silica rhyolite; this rhyolite grades upward into a thin crystal-rich quanz latite caprock. Data for these compositionally distinct zones are presented separately in Fig.11. Phenocrysts typically make up between 1 and 5% of the rock in the lower part of the member and make up 6-20% of the rock in the upper part (Fig.11a). Sanidine and plagioclase are the dominant felsic phenocrysts. Sanidine makes up >95% of all felsic phenocrysts in the rhyolite and 54 95% of all fehic phenocrysts in the quartz latite (Fig. lib). Quartz occurs only in trace amounts in both the rhyolite and quartz latite. Mafic phenocrysts in the rhyolite conrist of l homblende, subordinate biotite, and trace clinopyroxene (Table II). The quartz latite contair$ biotite, clinopyroxene, and small amounts of homblende. Accessory minerals in the rhyolite include Fe Ti oxides, abundant sphene, zircon, and apatite (Table II). The quartz latite contains i Fe Ti oxides, apatite, zircon, perrierite, and sphene. '~ '~ Microprobe data for the Tiva Canyon Member are incomplete, particularly for drEl hole l samples. Sanidine compositions in the rhyolitic portion of the member concentrate between Or33 l and Or42 f r one sample each from outcrop and from drill hole J 13 (Fig.11c). In contrast, two l outcrop samples of quartz latite have sanidine compositions that occur dominately between Or42' and Or50 (Fig. Ild). Sanidine compositions have not been determined for drill hole samples from o { L -
the quartz latiric ponion of the member. Biotite compositions for one quartz latitic outcrop sample range between Mg*g and Mg*70 (Fig.1Id). The modal data for outcrop and drill hole samples are very similar for the Tiva Canyon Member. The rhyolite in panicular is unique among all units at Yucca Mountain for the high proportion of sanidine that it contains (Fig. Ilb). Although data are sparse for the quart:latite,its increased plagioclase contents relative to rhyolite occur in both drill hole samples and in outcrop samples (Fig.11b). Except for sanidine compositions in rhyolite, mineral chemical data for the Tiva Canyon Member are too incomplete for meaningful comparison. In the rhyolite, the compositional range and dommant compositional mode for sanidine in the one outcrop sangle are the same as that for sanidine for one sample from J 13 (Fig.11c). \ VL
SUMMARY
AND CONCLUSIONS This report summarizes the available petrographic and mineral chemical data for stratigraphic units at Yucca Mountain to assist a potential review of the drill core by a peer review panel. A peer review is one method being considered to qualify the drill cores so that data derived from them can be used as primary data during the licence application for the Yucca Mountain site. Such a review is necessary because existing documentation does not meet QA requirements to provide comprehensive sample traceability. The method of comparing data for drill hole samples with data from well established surface exposures of the same unit is a widely accepted practice for making subsurface correlations in the oil and gas industry and in the nuclear testing program. This method is panicularly well l suited for confimung the identity of units in drill core from Yucca Mountain because stratigraphic relations for the region are so well known from surface studies. Except for the Older Tuff Units A, B, and C, the volcanic units underlying Yucca Mountain are known to also crop out in surface exposures. . Each stratigraphic unit has unique petrographic and mineral chemical characteristics (Fig.
- 12) and stratigraphic identifications based on these characteristics can be confidently made in most cases. Petrographic characteristics can have a relatively high degree of variability (e.g., Figs.12a and b) because of factors such as (1) poor representation of sample inhomogeneities by the limited surface areas of thin sections,(2) poor counting statistics in phenocryst poor units (e.g., Topopah Spring rhyolite and the upper part of the tuffaceous beds of Calico Hills),(3) mechanical winnowing and soning of pyroclastic components during emplacement of some units (e.g., bedded 19
tuffs),(4) vertical variations in rock composition in units erupted from compositionally zoned magma systems (e.g., Tiva Canyon and Topopah Spring Members), and (5) differences in porosity associated with degree of welding (e.g., compaction and welding decrease the porosity of the tuffs resulting in systematically higher genocryst contents in densely welded tu'fs compared to the nonwelded portions of the same unit). Despite these complications, careful consideration of a variety of petrographic characteristics including total phenocryst abundances, relative propon. ions of phenocryst minerals, and types and abundances of mafic and accessory minerals is an effective approach for uniquely identifying stratigraphic units. The mineral chemistry of phenocrysts is also an important means of distinguishing stratigraphic units, especially when used in conjunction with the petrographic data. Sanidine phenocrysts in particular have narrow compositional ranges for most units and often have distinctive dominant compositions (Fig.12c). Commonly, plagioclase phenocrysts are normally zoned from core to rim; because of this they typically have a larger compositional range than do sanidines which show little or no zonation. However, plagioclases have relatively restricted rim compositions that are useful for siratigraphic identifications (Fig.12d). Biotite compositions are less useful for identifying individual units, tending to be either relatively iron rich or iron poor for thick stratigraphic sequences made up of several units (Fig.12c). For example, the Crater Flat Tuffs, the tuffaccous beds of Calico Hills, and the rhyolitic part of the Topopah Spring Member are characterized by relatively iron rich biotite compositions. All other units contain relatively magnesium rich biotites. Although less specific than sanidine or plagioclase, biotite compositions provide an additional check for compositional consistency for the units described above. Petrographic and mineral chemical data, when used in combination with other geologic and geophysical information, provide a method for uniquely identifying stratigraphic units in Yuccc Mountain drill cores. Correct stratigraphic relations in the drill core provide a strong argument that the core was not severely compromised during its collection or storage. Although much of the data necessary for a peer review '.as already been collected, additional petrographic and mineral chemical data are needed to fully characterize the stratigraphic units at Yucca Mountain. A comprehensive characterization of both drill hole and outcrop samples will require a major effort on the part of the NNWSI Project. Because of the level of effort required to complete a comprehensive characterization, the NNWSI Project should commit itself to the peer review process as a means of qualifying the existing drill core before additional work of this type is undertaken. t9 S
t ACKNOWLEDGMENTS We are grateful to D. T. Vaa.iman for a helpful review of the manuscript, to B. Hahn for usistance in typing the manuscript, and to S. Dominguez and A. Garcia for drafting the figures. REFERENCES Broxton, D. E., D. Vaniman, F. Caporuscio, B. Amey, and G. Heiken,1982, Detailed petrographic descriptions and microprobe data for drill holes USW-G2 and UE25b 1H, Yucca Mountam, Nevada, Los Alamos National Laboratory Recon LA 9324 MS,168 pp.,1982. Byers, F. M., Jr., Petrochemical variation of Topopah Spring tuff matrix with depth (stratigraphic level), Drill Hole USW G-4, Yucca Mountain, Nevada, Los Alamos National Laboratorv Report LA-10561-MS, December 1985. Byers, F. M., Jr., and L. M. Moore, Petrographic Variation of the Topopah Spring tuff matrix. within and between cored drill holes, Yucca Mountain, Nevada, Los Alamos National Laboratorv Repo;t LA-10901-MS,72 pp., February 1987. Byers, F. M., Jr., and R. G. Waram, Revised volcanic stratigraphy of Drill Hole J 13, Fortymile Wash, Nevada, based on petrographic modes and chemistry of phenocrysts, Los Alamos National Laboratorv Report LA 9652 MS,23 pp., January 1983. Byers, F. M., Jr., W. J. Carr, R. L. Chnstiansen, P. W. Lipman, P. P. Orkild, and W. D. Quin!ivan, Geologic map of the Timber Mountain caldera area, Nye County, Neva.h, U. S. Geol. Survev Misc. Geol. Inv. Map I 891,1976a. Byers, F. M., Jr., W. J. Carr, P. P. Orkild, W. D. Quinlivan, and K. A. Sargent, Volcanic suites and related cauldrons of Timber Mountain.Ouis Valley caldera complex, southem Nevada, U. S. Geol. Survev Prof. Paper R19,70 pp.,1976b. Carr, W. J., F. M. Byers, Jr., and P. P. Orkild, Stratigraphic and volcano tectonic relations of Crater Flat Tuff and some older volcanic units, Nye County, Nevada U. S. Geol. Survev Prof. Paxr 1323,28 pp.,1986. Carr, M. D., S. J. Waddell, G. S. Vick, J. M. Stock, S. A. Monsen, A. G. Harris, B. S. Cork, and F. M. Byers, Jr., Geol ~ogy of drill hole UE25p#1: A test hole to pre Tertiary rocks near the potential nuclear waste disposal site at Yucca Mountain, southem Nevada, U.S. Geol. Surv. . Open File Rept. 86175,88 pp.,1986. Christiansen, R. L., P. W. Lipman, W. J. Carr, F. M. Byers, Jr., P. P. Orkild, and K. A. Sargent. The Timber Mountain-Oasis Valley caldera complex of southem Nevada, Geol. Soc. Ameries Bull.,88,943 959,1977. Delrymple, G. B., Critical tables for conversion of K Ar ages from old to new constants, Geolorv, 7,558 560,1979. 20
Kistler, R. W., Potassium-Argon ages of volcanic rocks in Nye and Esmeralda Counties, Nevada, i llE. B. Eckel, ed., Nevada Test Site: Geol. Soc. America Mem. I10. 251262,1968. Lipman, P. W., R. L. Christiansen, and J. T. O'Connor, A compositionally zoned ash flow sheet in southem Nevada, U. S. Geol. Survev Prof. Paper 524 F,47 pp.,1966. Maldonado, F. and S. L. Koether, Stratigraphy, struceture and some petrographic features of Tertiary volcanic rocks at the USW G-2 drill hole, Yucca Mountain, Nye County, Nevada, U.S. Geol. Surv. Open. File Rept. 83 732,83 pp.,1983. Marvin, R. F., F. M. Byers, Jr., H. H. Mehnert, P. P. Orkild and T. W. Stem, Radiometric ages and stratigraphic sequence of volcanic and plutonic rocks, southem Nye and westem Lincoln Counties, Nevada, Geol. Soc. America Bull., 81,2657-2676,1970. Quinlivan, W. D. and F. M. Byers, Jr., Chemical data and variation diagrams of igneous rocks from the Timber Mountain Oasis Valley caldera complex, southem Nevada, U.S. Geol. Survey Open-File Rept. 77-724, 9 pp.,1977. Scott, R. .nd M. Castellanos, Preliminary report on the geologic character of drill holes USW GU-3 and USW G-3, U.S. Geol. Surv. Open File Rent. 84 191,121 pp.,1984 Spengler, R. W., D. C. Muller, and R. B. Livermore, Preliminary report on the geology and geophysics of drill hole UE25a 1, Yucca Mountain, Nevada, U.S. Geol. Surv. Open File Rept. 79-1244,43 pp.,1979. Spengler, R. W., F. M. Byers, Jr. and J. B. Wamer, Stratigraphy and stmeture of volcanic rocks in drill hole USW-Gl. Yucca Mountain, Nye County, Nevada, U.S. Geol. Surv. Open. File Rept. 81 1349,30 pp.,1981. Sykes, M. L., G. H. Heiken, and J. R. Smyth, Mineralogy and petrology of tuff units from the UE25a 1 drill site, Yucca Mountain, Nevada, Los Alamos National Laboratorv Report LA-8139 MS,76 pp.,1979. Warren, R. G., Geochemical similarities between volcanic units at Yucca Mountain and Pahute Mesa: Evidence for a common magmatic origin for volcanic sequences that flank the Timber Mountain caldera, Eos Trans. AGU. M,896,1983. Warren, R. G., F. M. Byers, Jr. and F. A. Caporuscio, Petrography and mineral chemisuy of units of the Topopah Spring, Calico Hills and Crater Flat Tuffs and older volcanic units, with emphasis on samples from drill hole USW G 1, Yucca Mountain, Nevada Test Site, Los Alames National Laboratorv Report LA 10003-MS,78 pp.,1984 n
e List of Tables I. ~ Stratigraphy of Major Volcarde Units at Yucca Mountain, Nevada. II. Modal Petrographic Data for Volcanic Units at Yucca Mountain, Nevada.--
.h 6
k l 1 [ t i i j
. t
, 25
l l TABI.Z 1. STRA11GRAP}fY OF MAJOP. VOLCANIC UhT1'S AT YUCCA MOUhTAIN. NEVADAa i Thichess ' Strutignphic Unitb (m) IJtsolog/ l, Palatbrush Tuff Tive Canyon 27 114 Ash flow tuft compositional!y zoned. compound cooling Member urit nonwelded vitne bec: moderately to densely welded, devttnSed intenor with some vapor phase crysullizadoc. Yucca Mounuin 0-29 Asb 00s tuff; conmelded vitne top and base; panially welded Member devitn5C intenor with some vapor phase crystalhradon; preser.t under nortbern half of Yucca Mountam. Pab Canyon 0-71 Ash Oow tuf; no* welded to parually welded; present under Member northern half of Yucca Mounuin. Topopah Spnng 287 356 Asb Cow tuf; compositionally zoned, compound cooling unit e Member nonwelded tones at top and base and moderately to de::r.tly welded, devunard intenor with zooes of vapor phase crystallization: vitropbyres at top and base of unit. Taffaceous Beds of 29 289 Ash Oow tuf; noowelded to partiaDy welded; also includes. Calico Hills bedded tufs; thoroughly seotinzed at north end of atploration block: becomes vitric southward. Unit coastsis of rhyolice lava flows and imerbedded tufs in Paintbrush Canyon. Crater Rat Tuff Prow Pass 107 176 Ash Oow tuf; nonwelded tones at top and base; moderately Member welded, devitnSed intenor wts minor vapor phase crysullization. Bullfrog Member 67 187 Ash Gow tuff; compound cooling unit; noewelded top and base, nonwelded to densely welded interior mim thiebess and occurrence of welding tones highly variable. Tram M+.rnber 103 373 Asb Dow tuff; cempound cooling unit: zones of parcal to dense weldmg vary frorn dnll bole to dn11 bole; litic nch bm. Dacite Flow Breccia 0 110 Flow breccia. lava asf taffs: occurrence restricted to drill boles USW G 1 and USW G 2-Lithic Ridge Tuff 185 304 Ash-Oow tuEs: nonwelded to moderately welded; devici5e1 littuc rich throughout. _ T UnnamM older tufs 365+ Asb Dow tuEs. lavas, reworked volcanic sediments; dacitic to and lavas rbyohtic compositions; Includes units A. B. and C in dn11 boles USW G 1 and USW G 2. aSpengler et al (1979.1981). Maldenado and Koether (1983). Scott and CasteUanos (1984). b Volumerzically minor bedded tuffs bets een major stratigraphic units not sboss. 0
1
- i 1
. l TABLE II MODAL PETR0 GRAPHIC DATA FOR VOLCANIC UNITS AT YUCCA MOUNTAIN, NEVADA
,1e euse t .es;,1e c. .Ite.- .. tote m a u, a m u. ,elete a y e g 14t. Esmag. M 2221I ti1*S' Ceupted h I tuert hi (Eastl Volume tereest of Total hoch 4 et relegg t henoc rv e t eS y -e Cae ,ee teeman,r. totastrish Tu f f - Dooe r p a rt 42L-178 4 0 det D 1310 0.2 16.4 <1 10 30 42L-170-0 0 dwt 0 3540 2.1 14.2 2 75 23 rart-6 793370 $54260 0 et G1/mG 300 9.7 20.0 2 54 45 Fort 1 193310 554900 0 et 41/ mas 275 1.8 13.1 0 16 23 AGE-4 O det D 1011 0.0 12.3 0 et 12 SC-3 C 0 d et 0 1953 0.0 '5.1
. 0 to 6 03w ev-3-3s. 3 752690 S34501 C atto <0.1 15.0 1 69 30 USw CU
- 45.4 752690 554501 C 1640 <0.1 S.9 0 93 7 pe-2 Spit-210 156171 311485 Da 0.0 13.2 0 95 3
'ltwe' m* temmener. Palatbrwe4 Twf f - tower f o rt mm318-1 706070 S40000 0 det Aa/G /evy 512 0.4 0.0 4.1 0 99 1 SC-3 A 0 d et 0 6000 0.0 1.6 0 100 0 tm 1A . O det D 9620 0.0 2.1 0 100 <1 es -274e 0 et G1 1000 0.0 3.0 0 100 0 pe:-214C 0 det D 1000 0.0 4.4 2 98 0 Te42R 0 d et D 7247 0.0 2.0 0 100 <1 MC-299 0 *t G1 0 0.0 2.1 0 100 <1 csw co-3-78.4 752690 350501 C 1540 <0.1 2.3 0 100 <1 Osw @0-3 245.1 152490 554501 C 1580 <0.1 3.3 0 94 4 Osw 00 3 303.1 732490 $50501 C 1680 1.0 3.1 0 100 0 Usw S0-*=356.3 752690 S$4501 C 1550 (0.1 4.0 0' 100 0 pe-2Saft-03.1 764900 $66350 C evt evp 400 0.0 25.0 0.0 3.0 co-25401-157.3 164900 $44350 C det vp 723 0.0 0.1 0.0 3.6 De-2Sa41-101.0 184904 344350 C out avy 1004 4.1 21.0 0.2 4.6 + 13-427 149209 379451 C dwt vp 100 0.0 3.0 0 96 2 De-2Spft-110 156171 S11465 De 0.0 2.1 0 100 0 De-25p41 290 734171 $71405 Ce 0.0 1.5 0 100 0 1 t ie.e . .e. e ,e de .c u.e. i . f s o .. O to oe.e.a . tate Coe, dime e;st . i.cauen. not listed ie, eamqntes f rom pua&&ehed reporte for whis! secise sample localitise are lactang.
2 Sagle types inclinee ehele rest samples f a M evtcrop toi, pwalce lapilli f aan outcrop top), 4:111 core (01. j and 6:1.11 hit evttings tool . thenocryste e^f he artificially eeneentrated in eene drall bat cuttanget Oa t test aates emmples weere this se eespected one these date sete esetused freus the flyures. 3 Each typee imelade welded tuf f totle on M1ded tuf f (nwst, partially-welded tuf f (pest. moeerstely-wended tuC2 ta=ti, esmeely-weiseJ tuf f (dett e citrotnyre tet), lave (1), flow tretene (fbt, and beeded tuff (bl. 4 D = h.igh temperatore devitrification. *p = ophoruittle crystallisetien. Aa = estelitie crysta!!!satsen, Cr
- Teamepayaie cryst allisation. Vp a var phase alteration. Q = ealistlicassen. Ab = altit aset ten, py
- pyritasation, A. = argillic entreati' ce = caleafication, la = analstas seelatiset&oa, se e c1&nopt&1e14te see11tteattee. 0 = opal and 0
- analte*NS glassy pyrocleets remain Antact. The psefia 'e' la front of alteration type 4adAcates a ma .or emosat of that type of alterataen, j $ relei n then. = v arts (C), alta11 telderet (AF), and plagteelase (FI phenocryote se veluuna pettent of total reest these values wese seteruAned by standard peant counto for oil ennplee.. me. eves. 6m samples andacated by na asteria (*l, the preeertiese of C. at and P are based en reistive areas of the 30s largest telese l pheaw ry ot e tweeten et al. 4J04). In eene unite the eine distributaen vestes sabotentially among the fetesc
{ I phonettyst s, these f ese we emit these esta La figure s enewsag ro taL&re paspett aene of f eleac pnenMay ot s.
--_-- , - -,.nv ,,. -.-- -- -
TABLE II (CONT'D.) so-a w_u e m m ca .u n. aannt uaa- m a- m etit. u ,.e. w
.e mert Mau its easils tiefle- and heesseery-esameral ceaseatretiene la parte ver Itallieel Tive Caseen lessener, taisthresh Taf f = Weser tort 42L 178.A 9000 2000 S000 tr 2 12L*114*3 0000 1000 4000 0 3000 0 tr 0 0 0 0 2 rett *4 4800 120 2000 0 2400 370 20 0 37 440 190 3
. rerP=1 $100 410 5400 0 4400 220 45 0- 93 420 280 3 Act.4 SOCO tr 2000 0 4000 tr 2 pC=3 C 2000 0 2000 0 3000 tr 2 trsw 09-3 3 8.3 8050 0 te tr 1410 tr 0 tr tr tr 1 tsw 90-3*45.4 1860 420 te tr 420 tr O ts te tr i De-23p41-210 3231 0 4230- 0 .1430 tr 0 Le tr 3
~
e Ytee hw teoshen. Paistheneh Tuff = teser Part-aw31e=1 330 $$0 0 0 $10 11 450 0 0 21 34 3 8C 3 A tr 0 0 0 2000 tr 2 en 1A te tr 0 0 1000 tr 2 nce2140 0 1000 0 0 1000 0 2 mC-214C 0 .000 0 0 1000 0 2 te42R 1000 tr 0 0' tt 0 1000 0 0 0 0 2 nc.299 0 3000 0 0 1000 0 2 USW GUa3=78.4 to to 0 0 te tr 0 0 0 tr 1 Ufu 90-3*245.1 tr 1360 ?, O tr tr 0 0 0 tr ? Osw EU-3*303.7 0 t** 0 440 to tr 0 tr tr tr ? V9W 00*3*354.3 0 tr G 0 te tr 0 tr te tr 1 so.Ileft*03.7 4 pe.2Sof1=1b?.S 4 pe-3Sett+197.0 4 Ja13*427 44 080 0 0 290 0 230 0 2 4 19 3 pe=3Sp41 270 080 0 0 6 0 tr 0 tr te 3 go.23p41 290 0 0 0 0 0 tr o te tr 3 4 .;_ . 4 1 = Lipmen et al., 1944: 2
- Ovantavan one eyers.19?? 3 = thae reperst 4 = syk'ee et al.,'1919: 5 = e'yere sad seeren. 1943: 4 = dearen et al., 1984: 1 = Seest and Caste 11enes,194 4; ee syers, 1945, t = syere one senere, 1941 1 Caneestrations felle.e4 by 'pe' indarstes the manesel le altered one the eencontratten to beeed on poweemmerpner tr e trees teameral teentainee an tSan sert &on but St e eeneentsetten not estermaneel. A entry of tore &nd&eates e a4messi to me6 present: a blema andasetes se anternetten en a maneral'a presence er aheence.
l r .
TABLE II (CONT'D.) o g le s. meet te.1 aan,1. ae A. Iter- potet e ?. alga m Lituce reiste g g g gg &et. & amp. M 223'1I tilgg i Coast e4 f.k* L Wert h! . (Baet t vel m pereent of Total Sec 4 of reiste p henoc rv e t sS Tueen tenent ale Immmee r. felet. brush Tuff unsG2 ell 178160 S44100 0 ows 01/ mar /s0 320 14.8 1.2 0.2 0.1 0 59 41 9e4 Caavec lemmerer, paastatuat Tuff 4?re-1A 0 tot 1580 0.0 67r3-19 6.8 1 43 $4 0 pet 3500 0.0 4?rs 30 10.S 1 S6 43 0 evs 1500 0.0 10.0 67rs.3 t p <1 45 SS C evt 1550 0.0 10.1 0 41 53 8e-25e41-224.1 164900 566350 C ows $1/te '404 1.7 12.0 0 30 62 vsw s.2 501 170624 $60S04 C met 61 '6926 11.3 O.4 4.1 vsw 6 2 341 ??t024 $60504 C 2 30 "60 evt 51/ mat 6725 1.1 0.7 4.1 45 vsw G.2 561 178824 560$04 2 $3 C evt s.a/sp 6490 7.3 0.5 4.2 4 3? $9 Osw G-2*SO4 110024 $60$04 C pwt Aa/Sp/vp 1211 3.4 2.1 tsu 4 2*421 ??t024 560SO4 C 0.t 1 34 El rwt sp/vp 6414 0.4 0.4 ( 5 31 64 Wsw 4 2-61* 110024 560$04 C pwt D/te 644S 0.9 2.4 T.6 4 42 $4 Osw s.2 12:e 170024 560504 C met $1/ce 6426 2.0 4.0 1 SS 44 Tweesen seeLas temmepe r, peLetb rueh twf f - Spo's e e eet 61L-17.s o et Gl? 2892 19.0 1 61 30 AGE 2B C evt 0 23$1 16.2 1 65 31 A46 2A 0 et G17 2009 14.7 <1 65 33 38286 14 0 vs G1/mo 303 0.0 2.0 0.3 11.0 1 ft 29 aw31e-2 0 evt 61 502 0.2 3.2 , 11.0 S.0 0 60 40 sur2De 9 0 et 41 293 0.3 8.0 sur3te S Op 0 30 30 evt $1/mor $97 0.7 91.0 0.0 7.3 0 00 20 11+102 10 0 d et 0 2500 1.2 72 1 21 11-102=Tr 0 ews D 3400
- S.4 2 59 39 Osu 4-1*292 170500 S41000 C ews sp/Gr $644 3.4 0.3 10.0 0 61 32 Wee 9-1-303.1 170300 $61000 C ews SP/ Gr $229 2.0 14.4 0 13 26 95W 6-1=430 170500 541000 C ews sp/Gr $488 1.1 0.4 0 00 19 Osu G-ta??O 178824 560504 C det sp/Gr 1012 2.0 1.3 14.1 0 of 36 55W G=2*(22 110824 540504 C ews sp/Gr 5936 1.0 0.1 11.4 0 14 29 T'4e G-2-432 170824 S40$04 C det sp/Gr $400 S.3 0.3 16.1 0 12 21 Wsu 9-2 090 178024 $40504 C evt SP/Gr 454S 4.9 0.1 15.0 0 il 20 Osw G0-3=424.3 192490 358441 C 1888 3.0 S.6 1 St 40 Wsw GP 3 430.5 152iK 550501 C vs sp 5024 S.6 0.1 43.9 0 65 34 Wsw 00 3-430.1 TS1690 555501 C et sp/Gr $993 S.3 0.2 13.7 0 50 49 Ese 50-3-430.1 192690 230$01 C 1380 <0.1 15.3 <1 $2 48 vse 50-3-464.5 192490 550501 C 1500 <0.1 12.2 0 13 21 938 Gw 3 464.5 152690 350$01 C est sp/Gr/vp $322 3.3 12.0 0 15 24 esw Gg.3 46S.S 152490 SS8S01 C det sp/Gr/vp 52?? 2.4 0.1 12.4 0 it 41 937 GU-3-525.4 752490 $38501 C ews Sp/Cr/vp 5250 0.2 6,t 0 11 2e USu eg.3*S25.1 132690 530$01 C 1500
<0.1 4,6 0 15 23 98w G-4*241.4 145001 563082 C et Aa/G1 $229 1.8 0.9 10.3 <1 63 31 O s't 4 4 = 3 01. 6 165401 S43082 C evt sp/Aa/Gr/vp 5663 3.7 0.1 14.1 0 53 4' Dsw G.4*303 16S001 543002 C ews sp/Aa/Gr/vp $031 1.2 0.1 geu G.4 410 12.1 6 10 22 16550? S43002 C ews Sp/Aa/Gr/Vp Si4S 10.5 0.1 6.5 1 10 29 seu 6-4=416 165407 343082 C ews sp/Aa/Gr/vp 5217 0.1 0.2 0 44 36 4
l l
]
TABl.E II (CONT'D.) I i Saue19 M *t it t R SH pee 98 ff211 119 h @t 2,,e,,!,C Asettle liegen g6 owls e Au Ann.t ads fie. and &ces seery.441ase ral P'-
?t ratione la Part e ser bLL111 eat te+es tesemaaLa tauegr Pe>heson ts)]
suur.2 ell 27 0 0 0 al 0 4 0 0 0.3 11 3 Feh Cantes teamber. Paistbruah tof f 6?rs.1A 3000 0 0 0 2000 te 61/s.13 7000 0 2000 0 2000 tr 2 6?rs.30 4000 0 1000 0 3000 tr 3 6?rt.38 $000 2 0 tr 0 2000 Le se.23481 226.1 2000 2 0 $20 0 1400 25 22 0 29 SO 30 la vye 4 2 501 3200 0 430 0 1400 gau 6 2 541 tr 'O te te tr 3 3900 0 600 0 1800 tr 0 gau 6 2.S$1 tr te tr 3 4300 0 600 0 1200 tr e psu 6 2 584 te te tr S 5100 0 800 0 3200 tr 0 pew e.2 421 tr 44 te 3 5000 0 tr 0 1100 tr 0 tr te te 3 veu s.2 41$ 3100 0 200 0 2500 tr 0 te gew 0 2 723 te tr 3 2700 0 tr 0 900 tr 0 to te tr 3 Teemseh SeeLas sammeber, teLashreat tof f . Oswe'r 9 art 67L-11 5 9000 tr 4000 0 4000 0 1000 0 0 0 0 A02 23 0000 tr 1000 0 3000 tr 1 1 Ar.4 2A 7000 tr 2000 0 5000 tr celeb.14 2500 1 0 1700 0 1300 SCO 0 0 230 140 mw31a*2 120 3 1200 0 1400 0 1600 22 0 44 St 41 45 3 Sw294 9 1400 21 1200 0 J300 260 0 0 140 4?O 230 3 mw31a.S 940 0 130 0 830 320 0 0 110 32 42 3 11 102 70 3000 0 2000 0 2000 0 1 11 102.tr 1000 0 0 0 2000 0 1 033 0 1 392 7021 0 476 0 3213 0 O tet?) 9 ( vsw 9 1 345.7 39$2 132 1976 0 1612 0 0 0 9
- tru 6 1 430 2314 0 1846 0 534 0 0 0 9 i
Usw 6 2 110 12310 0 $130 0 4150 0 0 0 9 Stw 0 2 422 $373 0 112h G 22$0 0 0 trits 9 Urw G.2 8SS 492S 0 0 0 4375 0 0 ta tti 's Vfw 0 2 898 5530 0 1264 0 944 0 0 tr 9 l Osw sg.3 424.3 2340 te tr 0 $90 0 0 tr ts tr 7 l Ora 89 3 430.5 1294 152 2432 0 2S84 0 0 te(?l 9 l Osw 09 3 410.1 8092 0 $148 0 est0 0 0 0 . - 9-ggu 80 3 430.1 6400 0 3400 0 $100 0 0 te to ' "tr '1 TTw 00 3 464.5 $400 0 2140 0 60$0 0 0 te to tr . '1 1 l Tru 09 3 444.5 3225 0 3354 0 2322 0 0 0 9 Csu 80 3 445.5 4320 0 1080 0 1000 0 0 t e (?l 9 tru OU 3.S25.4 2479 0 1541 0 1139 0 0 0 9 Upw 00 3 523.1 1470 0 tr 0 1960 0 0 te tr tr ? I OSw 0 4 241.5 8591 0 3308 0 5929 0 0 tr
- 4 Ttw 0 4 301.6 11932 0 1254 0 1813 0 0 tr 8 93w 4 4 383 756 318 156 0 2394 0 0 tr e Osw 0 4 410 1156 0 612 0 1856 0 0 tr 8 U$w 0 4*416 163 595 935 0 lato 0 0 te e l
1 l k
TABLE (CONT'D.) wl. s as 1 esm,1. noen a2ter- potes e IaMa tanLas utuce rele** 9 E t me &*** %d'9 IIER1 IIES 25129 hH h m eesh L isaati volumn reramat of Tuul.Reca 4 of relate fbetettvetal g,.2Se#1*2$1.0 184900 166350 C b se/G1 442 0.3 4.2 1.5 0- to 30 p,.25 01-216.6 744900 S443$0 C evt 01 430 1.9 14.0 0 66 34 go.2140t*214.6 164900 186350 C et D/mol 4394 0.6 0.0 10.1 0 17 22 pe.2Seft=334.7 184p00 546350 C evt Sp/Gr 6404 2.4 15.2 0 16 23 J-13*400 149209 S196S1 C h ta 300 2.0 4.7 4.6 10 40 42 J.13 003 149209 5796S1 C evt er/vp 300 0.7 0.9 12.0 0 62 38 Tesomen earles tummener. Palathrash Twf f = Lower part
. 11 192*?9-A O det D 3400 0.7 0 43 51 11 102-?C o evt D 3500 0.0 1.2 11-132 7s o
<1 50 30 dwt D 3500 '
O.0 1.2 8 42 50 67L-120-e.1 0 kwt 0 $000 0.0 2.1 0 43 St 47L-11 0
- O evt D 20$5 0.0 4.8 <1 67 33 67L*11*P O evt D $671 0.0 1.9 5 65 30 47L-11 s O des D 5000 0.0 1.3 8 54 36 6?L=17-2 O ews D 6000 0.0 0.9 <1 44 36 Sw25 t 134290 572750 0 t G1 1841 41.0 20.0 4.1 1.1 0 39 61 sC*1t 0 det D 6500 0.0 1.1 <1 36 44 Tott-C O evt *O 6010 0.0 1.1 <1 le 32 sps 6 1 304 170500 361000 C evt sp/Gr 12284 0.8 1.6 0 $$ 44 trsw e-t-619 110$00 541000 C ews sp/Ge 11912 0.0 0.1 0.4 0 SS 44 Wsw 5-ta122 170500 $61000 C ews Sp/Gr 11382 1.0 0.6 0.5 0 36 43
+98u S-1-157 110500 S41000 C ews SP/Gr 12980 0.0 0.2 0.2 7 61 31 vsw 0-1=112.3 110500 $61000 C #ws Sp/Gr 12428 0.2 0.2 0.6 12 35 51 gle 5-1-795.6 110500 $61000 C ews Sp/Ge 12292 0.6 0.5 3 10 26 8 Wsw 9=1-009.9 170500 S61000 C twt SP/Gr 12512 1.0 1.3 1 46 45 93w G-1 035.3 170$00 561000 C ews sp/Gr 12206 0.3 0.9 1.0 4 39 86 sau 4-1*014.1 170500 S61000 C e=t SP/Ge 12136 0.1 0.2 1.2 1 36 s1 Tsu S=l*931.2 170$00 161000 C #ws Sp/Gr liste 0.4 0.9 9 37 52 Cru 6-1-995.5 170500 5610l# C evt SP/Gr 12534 0.9 0.9 4 24 49 . Esw 3-1-1049.1 170500 341001 C ews Sp/G 12442 6.3 0.9 3 46 50 vsw 4-1=1113.2 710500 541000 C evt Sp/Gr 12332 0.5 0.0 13 36 49 Dew 6-1*1150.3 170500 S61000 C det Sp/Gr 12394 1.3 0.4 8 37 54 Wsw 6 1 1191 170500 $6te00 C ews sp/Gr 11104 0.1 1.2 4 1 le Csw 6-teltti 170500 561000 C det Sp/Aa/sm3:4vy 500 0.0 32.0 1.2 1.8 1 0 91
- Cpv 6-1+1240 SY0500 561000 C evt SP/Gr 11296 0.4 0.3 1.1 4 13 19
, Csu S-l.1240 170500 $61000 C evt Aa/Gr/Sp SCO 0.0 27.0 3.2 2.6 5 13 42 + CSw 4-1=1206 170509 381000 C et SP/Gr/8e 19790 1.8 9.3 0.9 18 25 is vsw e-1 1296 110$ee 161000 C et 6p/Gr/te 100 0.4 13.0 10.0 1.7 to 46 30
- Wsw 6-1-1292 170500 S61000 C est SP/Gr !!a30 2.1 3.0 1.2 11 25 63 gru S-1=1292 179800 841000 C et 41 $39 0.0 22.0 *.S 0.9 10 11 13
- Csw o-1-1392 170500 361000 C n=t 61/ mat 500 0.6 20.0 1.2 0.6 3 1 90 e geu 6-2-951 ??4426 $60$04 C #wt SP/Gr 11400 ' O.S 1.4 1.0 2 SS 42 9pu 9-2-1932 174624 160$04 C #ws SP/Gr 11790 0.1 1.1 3 26 10 Csw 6-2-3012 118624 $80504 C ews SP/Gr 122'8 7.S 0.3 0.9 1 13 IS Csw 6-!=1170 170424 360504 C 1-t 8p/Gr 9342 1.9 0.4 0.4 0 42 51 C3w 6-2 1110s 174924 563104 C evt Op/Gr 9??6 1.6 0.8 0.4 0 37 62 U3w S-2=1234 170024 360504 C est 8P/Gr 9610 0.8 0.1 1 22 49 4
6
1 I TABLE II (CONT'D.) nasai imm a m. a amme um- um mt as tr_n m&se.g b W11.1
=t. mm ae j tanfie- and asemamer ,a" sa.1 *--- rati in Parte see taillisa?
De.2Se41 251.0 9200 0 1000 0 1300 0 0 0 120 252 ve*25e#1*2?6.6 6900 0 3000 100 1900 110 180 6 pe.25a41 276.6 0 0 68 110 12120 0 4400 0 110 6 2160 0 0 tr t ?l De-28641 334.7 $994 0 486 0 2592 9 0 0 t o t?) J'13*404 1400 0 0 0 1100 0 3 0 0 0 0 21 3 J-13 001 1000 0 0 0 1100 0 0 0 110 21 16 3 Temamah eseLas sammber. 7tiet.hrwh tuf f = lawse Part 11*102-it=A tr 0 0 0 1000
- 0 11*102-1C tr 0 0 0 1000 1 0
11 102 75 1000 0 0 0 1000 0 -- i 6th.120.s.1 tr 0 0 0 tr 4
** ^ 1 4tL-11-0 , 2000 0 0 0 3000
- 1 0
['1 6?L 11 F tr 0 0 0 1000 0 67L-11*n tr 0 0 0 tr 1 0 67L-11 2 tr 0 0 0 1000 1 par 23p-1 0 210 SS 0 2500 1200 0 1 0 0 0 100 0C+1s tr 0 0 0 tr SS 3 0 1 To41=C tr 0 0 0, 1000 0 Otw S.1=504 340 0 0 0 2210 1 V3w G-1*619 100 0 0 0 450 9 0 0 0 Osw 4 1 122 120 0 0 0 200 9 0 0 0 OSw G-1=157 ISO O O O 420 t 0 tr 0 t peu e-1 172.3 420 0 0 0 70 0 0 0 Osw S.1 199.6 380 0 210 0 160 t pse 4 1 009.9 0 0 0 206 0 0 0 200 t 0 0 0 vsw e-1 433.3 330 0 0 0 660 0 9 0 0 esa s.1 474.7 390 0 0 0 195 0 0 9 I 0 t tyw G-1*t31.2 660 0 0 0 305 0 0 0 Osw G=1 991.5 0 0 0 0 600 0 9 0 0 Urw 5 1=1049.1 800 0 0 0 200 0 t
- tr 0 trw S.1 1113.2 100 0 0 0 360 0 0 9
ess 4 1-1180.3 0 9
- 000 0 0 0 240 0 0 0 9 ysw s-1 1191 260 0 0 0 260 0 4r 0 tru s=1 1191 290 0 0 0 100 0 0 260 9
Stw 5-1*1240 180 0 4 21 6 0 0 0 420 Osw G-1 1240 240 0 t e sti e t 0 0 0 460 0 0 0 0 17 58u G-1+1286 200 0- 0 0 0 0 f 0 0 0 9 tra s.t 1204 190 1 0 0 310 0 1 - 0 0 0 9 c w 6-1=1292 130 0 0 0 130 0 6 6 0 0 Otw S 1*1292 200 0 0 0 110 0 t 0 2 0 2 0 gyw 0-1=1392 200 0 0 6 0 160 0 0 0 0 0Fw G-2*t31 440 0 0 4 13 6 0 220 0 0 0 -t 99w S*2*1032 400 0 0 0 360 0 ' 0 9tw G-2*1072 0 200 0 0 0 700 0 t 0 0 .. 9 , Dsw 4 2=1119 200 0 0 0 200 ' ,e 0 ~0 0 ;9 f 99w G-2*111th 100 0 0 0 0 0 0 Dsw e.2 1234 400 0 9 l 0 0 0 160 0 0 0 t f l E -
TABLE II (CONT'D.) a== pre si ttent amm ,1* aa 8ttee- s*Lat e ZaMa tulee M1 Mat **1 ate e g g Eness 1**- 3'*"*- Ems,2 g,,,3 g33,4 c,., e, - g, 5 m etn> <ames Tel en parenat of Tusal hoek t_et petete the.e.*4 rv e t 4A Wsw 9 2 1267.6 170824 560504 C dwt Sp/Gr 11004 2.4 0.7 0.6 9 45 44 vsw G.2 1331 178824 560504 C dwt sp/Gr 9152 2.2 6.0 1.2 gew s.2 1420 6 15 18 118824 560504 C d et sp/Gr 10S$2 2.3 2.8 1.0 11 22 64 csw 6 2=1441 170024 560504 C dvs sp/Gr 10924 1.9 1.1 1.0 7 42 50 Wsw G.2=tSS6 778024 360$04 C det sp/Gr 11092 2.0 1.3 0.7 7 25 67 vsw G.2-1505 774424 560504 C evt sp/Gr 10640 0.2 1.4 0.9 16 Usw 6 2-1634 178824 $60504 C vt 29 53 0/Gr/te 0010 0.1 0.7 4.3 7 7 85 esw G-2=1664 774824 560504 C et G1 10720 2.6 1.0 14 22 62 03v 90-3 525.1 152590 $58501 C evt sp/Gr/vp S424 0.7 3.6 0 41 34 ssw sv.3 633.3 152690 554501 C d wt 8p/Cr 12072 0.1 0.9 0 29 11 Oser SU-3=633.3 732690 S56301 C 1880 <0.1 1.2 0 32 .48 esu 90 3 633.4 152690 $$8501 C evt SP/Gr Stil 0.0 0.7 0 6t 3 Osw SU.3 498.S 752690 358501 C ews sp/G 11344 0.6 1.3 0 16 03 WSW GU-3 735.S 7S2690 $58501 C evt sp/Gr 12 24 0.3 0.0 2 59 35 Weer 80 3 749.1 752690 550501 C ews sp/Gr 11804 0.6 0.S 3 55 40 Usw 00-3*149.1 752690 558501 C 1500 <0.1 0.2 <1 "S TS vsw CU.3 769.2 ?S2690 550501 C evt sp/Gr 9734 0.4 0.7 0 28 11 j vsw 00 3 005.0 752690 554501 C ews sp/Gr 12260 0.0 0.5 0 !? 82 l tsu e0-3 829.9 152690 338501 C evt sp/Gr 12176 1.5 1.3 1.0 3 24 12 ysw so.3 877.6 152690 558501 C evt sp/G 12390 0.2 4.0 1.0 8 16 75 Urw CU 3-911.3 752690 558501 C det
- sp/Gr 12458 4.2 0.9 10 46 43 esu 09 3 954.9 752690 554501 C det sp/G 11560 1.0 0.9 11 4 40 Use CU.3 954. 9 132690 554501 C 1480 <0.1 1.3 0 $ 95 Osw 09 3=958.0 752690 555501 C det sp/Gr 10974 0.5 0.0 18 44 36 Osw 00 3-1019.1 752690 550501 C d et sp/Gr 11836
- 2.7 0.9 9 35 54
, Osw S0 3 1079.4 752690 $58501 C ews Sp/Gr 11246 1.2 1.5 0.0 6 43 30 l Osw eu.3-1130.3 732690 $58501 C det sp/Gr 6(41 0.S 4.8 0.9 13 23 63 l csw S0 3 1130.4 752490 584501 C e-t sp/Gr 0243 0.4 1.3 1.2 11 28 59 vsw 89 3 1130.4 752690 558501 C 151w 4.0 1.1 11 28 41 Osw 00-3-1151.1 752490 358501 C ewt sp/Gr 11820 0.5 4.8 0.6 3 23 13 vsw 00 3=1114.9 152690 Sits 01 C ews sp/Ge 5076 0.5 7.9 1.4 0 60 to
. Osw 30 3 1195.9 TS2490 558501 C et sp/Aa/se 5065 0.5 S.9 1.6 24 22 52 vsw 30-3 1226.8 152490 538501 C vs G1 11354 0.5 3.5 0.9 9 to 29
( vsw 80 3 1226.9 752490 158501 C 1630 2.0 1.3 9 43 40 vsw 00 3 1302.6 752690 558501 C 1480 8.0 1.3 10 39 51 pew e.4 447 ' 763001 $43042 C ews sp/Aa/Gr/vp 6288 0.1 2.5 <1 33 47 l Wsw 6-4 500.9 145007 563082 C evt sp/Aa/Gr/vp 12440 0.5 0.4 0.6 9 15 17 ' Tsw S.4 514 143007 $43081 C ews sp/Aa/Gr/vp 11344 3.5 0.0 1.3 1 53 47 ese e.4 354 145007 363082 C dwt sp/Aa/Gr/vp 11900 8.0 0.0 0.6 0 20 00 Osw 0 4 62S 765007 563082 C ews sp/Aa/Gr/vp 11112 1.5 1.3 1 51 48 95W C-4 625.7 145007 343082 C ews Sp/Aa/Gr/vp 11112 0.1 0.9 0 22 ft Use 6 4 677 165807 $43002 C ews sp/As/Gr/vp 11248 0.1 0.5 0 23 ?? Osw G-4*694 165407 563042 C ows sp/Aa/Gr 11322 0.2 1.0 1 23 76 Ofw G 4 746 765807 543082 C m sp/Aa/Ge 11255 0.1 0.4 <1 34 se Osw 6 4 017 145907 563002 C det sp/Aa/Gr/vp 11530 0.4 1.5 3 21 76 Tsw G-4 934 765807 541602 C ews sp/Aa/Gr/vp 11872 0.6 0.0 5 25 to Osw S-4 1026 165887 $43082 C det sp/Aa/Gr/vp 10804 0.2 1.3 0.8 10 26 64 Tsw 5-4=1009 765801 563082 C r et sp/Aa/Gr/VP 11794 0.6 0.3 7 23 10 lsw G.4 1117 165007 $63082 C det sp/Aa/Gr/vp 10110 0.1 1.9 1.1 1 34 65 Osw G*4 1190 165607 563082 C det sp/Aa/Ge 9794 0.2 1.2 1.4 11 30 St l l l l l
TABLE II (CONT'D-) M Bietite R DE kg 13 D MS 390 # 8 M.Lg n, gg,gg,. ametits g g4 tantsz he.es.t Als ht112 aanfle and :eerea -ea.1 -_ rat Lu.e La sart s ser asa111eeT vsw G-2-1261.6 105 0 0 0 315 0 0 0 9 Osw 4 2 1331 420 0 0 0 130 0 0 0 9 WSW 0 4-1420 360 0 0 0 330 0 0 0 9 Osw C 2 1461 es? O O 0 0 0 0 0 9 Osw 4 2-15 5 6 0.0 0 0 0 160 0 0 0 9 Osw S 2-1585 400 0 0 0 100 0 0 0 9 Osw G 2 1434 440 0 0 0 320 0 0 0 9 08W 6-2-1644 275 0 0 0 215 0 0 0 9 Usw G7-3-525.1 497 0 0 0 1482 0 0- 0 9 Osw CU-3 433.3 200 0 0 0 400 0 0 0 9 veu 50-3-633.3 400 0 0 0 tr tr tr 0 tr tr 1 Dow ev-3-633.4 540 0 208 0 to e tr 0 .. 9 Osw Gv-3-494.5 150 0 0 0 300 0 tr 0 , 9 , Osw 50-3 235.5 299 0 0 0 90 0 tr 0 . . . 9 - psw eU-3 149.1 300 0 0 0 420 0 0 0 9 vsw 40-3-149.1 tr 0 0 0 600 0 tr 0 te tr .t Osw 0U 3 769.2 0 0 0 0 640 0 0 0 9 Oss sv 3-805.0 645 0 0 0 420 0 tr 0 9 csw 30-3 829.9 165 0 0 0 33 0 tr 0 9 esu so-3-t??.6 220 0 0 0 110 0 0 0 9 esw CU-3-911.3 350 0 0 E 100 0 0 0 9 Osw 8V-3-954.9 0 0 0 0 200 0 tr 0 9 Wsw GU-3-954.9 700 0 0 0 tr 0 tir 0 te tr 1 Usw SU 3-958.8 90 0 0 0 360 0 tr 0 9 tsu GU-3-1019.7 400 0 0 0 100 0 0 0 2 vsw OU-3-1979.4 210 0 0 0 630 0 tr 0 9 vsw CU-3 1130.3 300 0 0 0 SCO O tr 0 9 est 0U-3-1130.4 420 0 0 0 960 0 tr 0 9 Wsw OV 3-1130.4 tr 0 0 0 tr 0 tr 0 tr tr i seu GU-3-1151.? 320 0 0 0 1120 0 tr 0 9 vsw sU 3-1114.9 ISO O 0 0 600 0 0 0 9 Osw su-3 1195.0 110 0 0 0 340 0 tr 0 9 Osw 50-3-1226.8 300 0 0 0 400 0 tr 0 9 Osw GU-3-1224.9 600 0 0 0 1200 0 tr 0 tr tr 1 gew sc 3-134* 6 1920 0 0 0 640 0 0 0 te tr 1 tsu S-4-441 Ste 9 tr 0 260 0' 0 tr 4 tsw 6-4-500.9 J10 0 0 0 140 0 0 tr - t Tsw 4-4-514 420 .0 140 0 420 0 0 0 s I tsu 8-4-556 120 0 0 0 0 0 0 0 -s-Usw e-4 42$ 210 0 210pe 0 560 0 0 0- 8-I i Tsw C 4-425.1 600 0 0 0 SCO w 0 0 e Osw 4 4 4?? 300 0 0 0 120 0 tr 0 _ 8 Osw G 4-494 770 0 0 0 110 0 0 0 4 Usw 0 4 746 100 0 0 0 300 0 0 0 t Tsw G-4-017 160 0 0 0 000 0 0 0 t , Osw G 4 934 210 0 0 G 100 0 tr 0 e i stw G 4-1024 $40 , 0 0 0 100 0 tr 0 e-gru G-4 1089 240 0 0 0 200 0 tr 0 8 stw G 4 1111 400 0 0 0 120 0 te o e Osw 9 4 1190 0 0 0 0 210 0 tr 0 0
/
TABLE II (CONT'D.) wie 5,semateel se$ple mesa alsor- telese raisa 22sats I.atn.1ce relaae g g g Erets 8**. Same . M 222 3 tilin' C+=*4'4 '"** maath) (Raet) gg}; e perseet of Total tesa 4 et potste h E11115 psw e.4 1244 163907 $63002 C Sp/u/Gr 10250 det 2.6 1.2 27 11 56 09m G-4 1202 165007 563082 C det sp/Aa/Gr 10234 0.1 1.4 1.6 psw s-4-1299 765001 S43002 C 1 35 to et 01/1e 9920 0.3 3.2 0.9 5 10 gem s.t.1311 145801 Sf3002 15 C et G1/te 9042 3.J 1.1 13 21 46 ogw 6 4 1331 165007 S63082 C vs G1 10133 1.9 0.9 11 31 46 vsw s.4 1390.2 145007 543002 C not G1/te 4914 1.1 0.4 gav 4 4=1400.4 0 $3 66 145807 543082 C nwt G1/te 5314 10.6 0.f 5 21 61 De-25e f t.4 50.1 164900 546310 C e ws sp/Gr 6359 0.2 2.2 1 56 pe=2Sa41-449.2 184900 546350 C 42 det sp/Gr 4222 1.1
- 0.5 2.4 0 59 pe.25 eft 510.4 744900 544350 40 C evt sp/Gr $280 2.2 0.3 0.5 0 11 82 0 ,-25ef1 609.6 164900 $44350 C evt sp/Gr 5511 0.0 pe.25 eft-451.6 764900 566350 C 0.1 0 12 11 dwt sp/Gr 10544 0.1 0.5 0.9 0 24 75 De.2Sett=472.5 164900 564350 C dwt sp/Gr 12012 0.4 0.2 0.4 0- 22 11 De.25401 677.2 164900 $66350 C #ws sp/Ge 12272
- 0.1 0.1 0.6 2 41 Sa go.2Se#1-141.0 164900 566350 C et sp/Gr 12400 0.2 0.2 0.5 1 36 62 pe.2Seft.132.6 164900 S44350 C d et sp/Gr 12930 0.3 0.3 0.6 3 32 44 De=2Se01-744.1 164900 564350 C dwt sp/G 12430 0.5 0.5 0.9 5 23 64 se-2Se#1 036.0 764900 $44350 C dwt sp/Gr 13546 0.4 3.9 0.5 3 22 13 De.2Satt-440.1 764900 S44350 C evt Sp/Gr 11402 0.4 1.5 1.0 0 23 16 De-25e41-018.9 144900 $44350 C #ws sp/Gr 11910 10.0 0.1 1 19 49 9e=2Se t 1 0 9 4. 0 144900 S46350 C det Op/Gr 11030 0.2 0.5 3 32 63 pe.25e01 937.3 164900 $64350 C twt sp/Gr 12392 0.7 1.3 3 19 ??
De=25e41 1011.1 184900 $46350 C ews sp/Gr 11914 0.2 0.2 1.0 4 34 61 te=2Sa01-1960.1 164900 546350 C ewt sp/Gr 12000 0.9 0.4 0.6 2 13 64 pe.25e#1-1112.5 144900 $64350 C det sp/Gr 12242 0.1 0.7 0.4 1 31 SS so.2Se01-1152.6 164900 S45350 C dwt sp/Gr 18140 5.0 1.3 17 11 sl De=25elt=1195.2 744900 $44350 C set sp/Gr 12400 1.6 0.9 11 29 St De-2 Salt =1264.4 144900 S44350 C et sp/Gr/te 11584 1.1 16.7 0.0 21 21 et so-2Se 41-1279.2 16 4 900 544350 C vs G1 18650 0.2 1.1 1.2 15 27 57 De-2 S p41-420 754171 $11485 De det vp 0.0 2.6 0 52 48 f.e.25 pit.500 154171 511408 Da evt 0 0.1 0.3 0 S4 44 pe=25p01 910 158111 571485 De det c 0.4 0.3 0 41 S0 De-2Sp41-1050 154111 51140$ De det D 11.3 1.3 5 49 44 De 25pel 1150 ?$4171 $71403 De et G1 2.1 1.7 to 32 49 hiteesses sede of Callee title = es,er perg 3 15-02-5 186500 SS1000 0 n-t te 4645 11.3 3.1 2.9 35 32 31 315824 706400 551100 0 met to 4214 9.4 6.2 2.2 34 30 36 3-15-02-1 194350 SS1200 0 n et te 4514 3.9 1.0 1.0 3 15-42 0 43 26 31 194350 551200 0 n-t to 4601 6.5 1.0 2.1 49 30 21 3-15-02*9 186700 SS1400 0 n et te 4?22 6.9 0.0 1.6 22 24 $1 4-16 05 3A 707000 S73900 0 1 G1/te $319 0.7 0.0 4.8 30 33 16 4-16 05-4 781150 $14025 0 art te 4994 3.9 4.1 2.1 SO 22 20 4=16-05 5 184100 574400 0 1 G1/ esp /ete 5210 0.1 0.2 1.4 44 13 33 4*16 45-6 194800 S?SOM
- 1 G1/msp/m2e $297 0.1 0.0 1.5 38 50 12 4-16-05 0 184100 573400 0 b te $164
- 3. 0 2.6 2.7 25 43 32 d 16 05-9 704675 $75150 0 1 G1 S193 0.0 0.0 1.9 14 ,29 S1 4 16 45-12 197050 57f450 0 1 G1 5719 0.1 0.0 USw 4 1=1436 710500 S41000 1.4 30 51 20 C n-t te 100 11.0 29.0 Wrw e.1 1541 3.2 4.8 $6 22 22
- 170500 541000 C not te 500 5.0 41.0 2.0 2.4 USw G-1=1541.0 170500 $41000 C n-t 52 22 26
- te 3?SO 2.6 2.2 43 16 41 1
l l
TABLE II (CONT'D.) SamIe R&t$11,1 R h h I.0 Il ME h h lif.F.* & M.1119 3$tt9m E 6 M M 11.1 AS.LAlt lan f te and &senseer -talantal *-trati 1.a parts ser IsillieeT cre e-4 1244 900 0 0 0 420 0 tr 0 Osw s-4 1292 170 0 0 0 930 0 tr 4 0 Osw G-1-1299 300 0 0 0 300 0 s tr 0 Osw 0 4-1311 330 0 0 0 110 0 s tr 0 Osa $*4 1331 500 190 0 0 100 0 3 tr 0 t Oru S.4 1390.2 200 0 0 0 600 0 tr 0 F1m 0 4 1400.4 210 0 0 0 350 0 tr 3 tr 0 Os=2Saft-450.1 1040 0 0 0 240 0 tr 3 De=2Se81-469.2 1400 0 0 t r t ?) 9 0 0 2240 0 pe=2Se41-810.4 0 te tfl 350 0 0 0 100 0 9 0 0 9 Do.2 Sell-609.6 320 0 0 0 400 0 0 po-2Se01 431.6 0 y 110 0 0 0 330 0 0 0 pe=2Se41-472.5 240 180 0 0 400 9 0 0 0 De.254ft-6??.2 140 0 0 0 210 0 0
-9 po-2 5441 701. 0 0 9 150 0 0 0 490 .,0 '
, 0 0 ~9 De.2Se01-732.6 TO 9 0 0 !?S -0 0 0 De.2Se(1 744.1 500 0 0 0 200 0 0 9
po-25e#1-836.0 0 9 150 0 0 0 480 0 0 0 De-2Sett-448.1 Sec 0 0 0 220 0 0 9 0 0e-25441-076.9 300 0 0 0 300 0 9 tr 0 9 De.2Seft-094.0 240 0 0 0* 240 0 gr 0 pe-2Saft-931.3 400 0 0 0 600 9 0 0 0 De-2Se01-1011.1 330 0 0 0 110 0 9 pe=2Seta-1060.7 70 tr 0 9 0 0 0 350 0 0 0 De-25 ell =1112.5 210 0 0 0 10 .4 0 9 0 9 De-2Se81 1152.6 0 0 0 0 140 0 tt 0 De-25e01-1193.2 200 0 0 0 300 0 tr 9 0 De=25 eft-1264.4 360 0 0 0 100 0 0 0 9 De-2Se#1-1279.2 260 0 0 0 650 0 tr 9 pe.25p41-420 0 9 1000 0 0 0 0 0 0 0 tr 3 De-25p41-540 0 0 0 0 400 0 0 0 De=2Sp(1 910 0 0 0 0 500 tr 3 0 tr 0 0 pe.25p41 1030 200 3 0 0 0 420 0 0 0 0 3 po-25pfla11$0 1520 0 0 0 0 0 0 0 0 3 Tstfeemoso tede of Caltee title - Unmer f ort 3-15 02 5 400 0 0 0 tr 0 0 0 3 15 42-6 tr 0 0 0 tr 0 3 tr 0 3-19-82-1 tr 0. 0 0 tr 0 3 0 0 3-15 02 8 400 0 0 0 100 0 0 3 3 15-42-9 0 3 1900 0 0 ,0 400, O tt 0 3-4 16 95 3A 3200 0 0 0 tr 0 tr 0 3 4-16 05 4 400 0 0 0 209 0 tr 0 4 16 45 8 000 0 0 0 200 0 tr 3 4 16 05 4 0 3 400 0 0 0 400 0 tt 0 4 16-85 8 000 0 0 0 200 0 3 0 C 3 4 16 03-9 2100 tr 0 0 200 0 tr 4-16 45 12 0 3 500 0 0 0 tr 0 tr 0 Orw G 1=1436 210 0 0 0 110 0 3 0 0 0 0 83w 0-1 1361 ~300 0 0 0 110 0 0 0 4 4 0 0 Osu S.1 1561.8 270 0 0 0 0 0 0 2 5 0 0 0 4
. ll
TABLE II (cont'd.)
,1. S 11 41. n= a24. - e.t.t. 2:1.sa em e. utuee '***'e e M t m s.t. s ,. ,,2m2 . Im 3 ants' meetn> <a..t>
cast ed m' Teluma Pe eest of Tot &1 noch 9 et Felske thenocrvetel tme s.l 1639 770500 S41000 C aws se 500 2.4 40.0 1.4 3.4 vss 6-1-1649.5 770500 541000 C mwt sc 0000 54 17 25
- 1.9 2.0 $1 24 25 ess G-2-1710 778424 540504 C aws te 5000 1.6 1.4 41 to vsw on-3-1413.1 752490 $$4501 C 1440 2.0 2.9 it esw co-3-1439.4 152490 $58501 C aws 41 16 32 32 S100 1.4 0.7 38 38 24 asu 90-3-1439.5 7526 90 SS4501 C 1500 2.0 2.0 25 Usw G0-3-1439 S 152690 550$01 C mwt 01 5150 39 36 S.2 1.3 64 23 13 Usw su-3-1490.4 752690 $38$01 C nwt te 1400 2.0 1.8 pser 6-4-1472.2 76S807 $43002 7 6) 30 C not se 5547 2.5 1.6 39' *34- 23
, Tuf f agegas Seda of CAlice Bills - tower Part -- .
SWG2a-7 0 b te 447C 3.4 17.3 32 10 53 82re-1 799700 S49100 0 aws te 1580 3.9 7.8 02f8 2 189200 $49400 37 ' 26 37
- 0 nwt te 1595 9.5 1.1 16 19 53 82FS.)A 789300 $49800 0 avt te $400 4.0 1.5 26 22 52 92rs-3s 189300 S49800 0 aws le $200 7.1 9.3 31 26 42 IPS 2 t >=13 736400 639390 0 b 8e 338 2.7 S.3 6.9 40 13 41 3-15-82-1 186100 550000 0 aws 8e 553 4.0 18.0 17.0 23 67 to 3-15-02 3 706600 350900 0 '
s te 2374 S.3 3.3 7.4 vsw s-1 1774 770500 561000 b 31 33 34 C se 100 3.4 23.0 3.0 25.0 32 14 54
- vsw G-2-22t1 170424 560$04 C aws te 2750 3.4 S.O 40 30 22 Wsw 6-2-2328 710024 540504 C not le 180f 6.7 6.0 42 35 23 Wyv s-2-2358 710924 560504 C not te 1100 S.6- S.6 S6 IS 29 U3w 6-2-2449.? 770024 540504 C nwt te 1860 S.9 10.5 37 21 42 vsw 6-2-2534 718824 560504 C not te 1450 S.1 9.2 33 24 41 gru s-2-2551
- 170824 560504 C net 8e 1450 6.0 10.6 34 20 46
( l pse 6-2-2602.5 778824 560504 C not le 1450 S.4 14.9 35 20 el csw s-2 2650 110024 $60504 C nwt se 1300 3.4 20.2 37 22 41 Usw 00 3-1537.4 752690 SSIS01 C nwt 41 S200 S.9 20.9 31 13 SS asw 30-3-1571.5 7526 90 $58501 C mot 41 3163 1.0 7.9 20~ 37 43 prow Pase emmebee. Crete. Fiat Tuff o-1-70-13 0 4100 0.0 10.7 11 33 56 CTS 20 0 1410 0.0 13.1 22 40 39-mar 31a-4 706350 S36740 0 avt vp $97 13.0 0.2 4.9 25 31 41 susC2e-3 708510 530250 0 dwt 01/4. 516 0.0 23.3 0.8 16.0 to 45 41 tsw G-1-1011.7 ??O300 S61000 C pet 8e 3600 0.1 6.2 Il 93 32 tsw G-1-1920 770500 $61000 C pet te 500 2.5 21.0 1.4 1,3 12 43 45
- Wsw 0-1-1854 170500 $61000 C pwt to 484 3.1 25.0 1.0 11.0 15 39 44
- Usw s-1-1884 170500 361000 C pet As/3P 500 0.4 26.0 1.0 16.0 13 46 41
- Usw 6-1-1943.4 770500 541000 C art Yp 3350 0.4 14.4 13 39 44 Wsw G-1-1943 770500 361000 C mt Aa/8p 500 1.0 24.0 0.4 11.0 0 49 43
- Usw G-1-2009.8 170500 $61000 C pet 3750 2.6 7.9 15 47 38 Osw G-1-2003 770$00 541000 C p=t te 500 3.9 21.0 0.6 9.6 to 42 40
- Usw G-1*2124.7 770500 $61000 C net 3400 0.6 a.e 6 50 de l Usw G-2-2706 779024 560$04 C m=t 1450 0.3 9.7 13 54 33 l Usw e-2-2?SS 770824 $60504 C pwt 1500 0.5 13.2 14 41 43 Tsw G-2 3042 178824 $40504 C pet te/Ae 1630 1.3 13.0 16 41 36
, Osw G-2-3064 770824 $40504 C ==t le 1650 2.3 13.5 0 4S 47 l csw s-2-3108.1 770424 560504 C pwt le 1500 1.8 12.1 4 35 41 Dsw G-2*3122.2 170824 540$04 C ows 1500 0.7 11.2 9 $4 3' csw g-2 3143.5 710024 560$04 C rwt sc/Ae 1470 2.4 11.2 11 49 39 l l
TABLE II (CONT'D.) mi-R3ntit Diali. m as as ti-n u. aann me- em- u.t n e mte2 ~m 6 9mus.t LLa &ault sesfie- and neeeeeerv-411aeral caseestrations la part s ser at1111ee T ces s=1-1639 150 0 0 0 320 0 0 0 0 0 12 6 vow 8-1-164 9.3 375 0 0 0 125 0 0 0 0 tr 6 Osw e-2-1110 144 0 0 0 0 3 Osw 00 3=1413.1 1200 1200 0 tr tr 0 0 0 tr te t Osw e0-3 143.9.4 160 0 0 0 320 0 tr 0 3 Tsu 80*3-1639.$ 630 tr 0 0 tr 0 tr 0 te tr 1 vs's SU-3-14 3 9. S 840 0 0 0 0 Wyu OU 3-1490.4 tr 3 0 0 0 tr 0 tr 0 0 tr 1 98w 6-4-1472.2 340 0 0 0 170 0 0 tr t ?) 0 3 Taf te,eese tede of Calles tills - tweer part - ' * ' 1 muG2a-7 13724 0 0 0 940 0 0 0 tr 3 82r3 1 5712 0 0 0 412 0 0 0 4273-2 2409 0 0 0 tr 3' 0 0 0 0 0 3 SFTS 3A 6132 0 0 0 1848 0 0 0 tr 3 82rs-3s 7100 0 0 0 200 0 0 0 tr 3 Ds28tr=15 420 460 49 $10ee 400 41
- 10 0 0 12 3 3-15 02-1 12700 0 0 0 1800 $ tr 0 3 3-15-82 3 1700 0 0 0 tr 0 0 0 3 Usu C-1-1714 3000 0 0 0, 1100 0 0 0 0 11 $3 6 Usw G-2 2261 2344 0 0 0 311 0 0 0 tr tr 3 yeu S-2 2326 1260 0 0 0 1990 0 0 0 tr tr 3 Osu e-2-2354 8255 0 0 0 910 0 0 0 tr 3 gav s=2 2449.1 4290 0 0 0 080 0 0 0 tr 3 grw 6-2 2304 6231 0 0 0 493 0 0 0 tr tr 3 esu 6-2-2551 7390 0 0 0 1380 0 0 0 tr tr 3 Tsu e-2-1602.0 10333 0 0 0 0 0 0 0 tr tr 3 erw e-2-2650 10642 3052pe 0 0 2390 0 0 0 tr tr 3 Osw GU 3-1537.4 4880 3440 215 645 2195 0 tr 0 tr 3 Osw C0-3-1371.S 3632 tr 0 415 147 0 0 0 tr 3 true pass seemeper. Creter Flat taff 0-1-70-13 2000 0 0 0 2000 0 2 CFS20 1000 0 0 4000 3000 0 , - 2 -
asr31a-6 150 13 0 pe 1200 0 0 9 0 12 23 4-awG2a-3 060 310 0 4800 1400 0 0 350 0 $4 46 6-Usw 9-1-1911.1 200 ps 0 1900pe 360 0 0 0 0 tr 6 I vsw G-1-1820 210 0 0 pe 450 0 0 0 0 0 10 6 Usw G-1-itS4 500 3 0 ps 660 0 0 0 0 1 28 6-gru g-1-1984 $80 0 0 pe 1200 0 0 0 0 0 to 6-Urw G-1-1943.4 210 0 0 910pe 610 0 0 0 0 tr a Use 0-1-1983 1 0 0 0 1300 0 C 0 0 0 9 6 Dew G-1-2009.9 200 280 0 2100pe 530 0 tr e te tr 6-Esw G-1-2003 ps 0 0 pe 610 0 0 , 62 0 0- 13 6 e: Esw G-1-2124.1 280 pe 'O O 1100 0 tt 0 te tr .6 - Otw G-2 2100 1414 2121pe O ps 0 0 0 0 0 tr 3 Esw G-2 2155 6IS 3200pe 0 pe 1310 0 0 0 0 tr 3 ttw C-2 3042 tr 0 0 tr 655 0 0 0 0- tr 3 Esu 4 2 3044 tr See 0 2961 2395 0 tr 0 tr tr 3 Esw S-2 3108.1 0 634 0- 4044 1397 0 tr 0 0 tr 3 gru 0 2 3122.2 tr 0 0 0 1354 0 0 0 0 tr 3 Otw 4 2=3143.S 610 0 0 0 618 0 tr 0 te tr 3
~'
lh
TABLE D (CONT'D.) Sample Lesetteel Sa$ple tech Mter- Falst e 4 9 13 f.Ml.ll1 ka t hl e
- Felete g g g peg 3,e t . Leag. M gg333 ggie' Cownt ed P he n I tuers hi (Easti velume percent of Total tec.k 6 et telete 3
f be **e rv." 1 Tsw 4=;-3159.4 118824 $60504 C not 1500 2.6 to 9.4 7 43 49 Wsw 4-2-3216.7 110024 $60504 C met le 1500 0.0 6.? 14 30 SS tsu 6 2-3244.4 116624 $60$04 C net le 1500 2.4 S.9 17 39 e4 Wsw GU-3 1511.1 752690 338501 C 1530 1.0 1.2 14 46 40 psw gg.3 1598.9 ts2690 $54501 C 1300
- 1.0 4.4 11 32 51 934 50-3-1603.2 752490 $38501 C 1880 1.C I.1 6 39 SS ese 60 3-1744.0 152490 $54501 C 1200 2.0 10.4 15 11 St peu ev=3-1813.0 752690 550501 C 1480 3.0 9.9 1 34 56 vow ev-3-1986.3 752690 $50501 C 1400 2.0 0.S 1 to 44 tsw G-4-2069.0 765007 563002 C pwt le $006 1.0 0.8 6 30 $6 Wsu 0-4-2216.7 165807 $63092 C aws te 5482 2.2 1.1 9 46 45 ge=25 eft-1852.1 164900 $64350 C vs evp 298 0.0 43.0 0.7 9.0 pe=25 eft-1849.1 164900 $66350 C wt avp 300 0.0 36.0 0.0 9.6 se=2Se#1-1930.S 164900 564350 C wt avp 505 S.3 9.9 0.4 13.1 po-2Seft-2001.1 164900 566350 C det 8p 300 31.0 0.3 0.0 12.7 to-2Se41-2007.1 744900 3643SO C owt te 300 0.0 10.0 S.0 13.0 pe=2Seft-2113.6 164900 564350 C ews se S01 0.6 24.0 1.4 7.6 9e=2Saft-2220.4 764900 546350 C n-t te est 0.0 11.0 1.7 1.1 ge 2Se41-2304.6 764900 5643SO C not te 300 0.0 18.0 S.0 9.4 l se=2Se#1-2331.5 764900 564350 C met se 300 0.0 2.7 2.0 6.0 J-13-1982 149209 $794$1 C pet
- As/ce 300 1.0 19.0 11 40 43
- J-13-1883 149209 $196$1 C 1.6 9.4 11 56 33 J-13-1592 149209 5796S1 C b 8e 300 1.0 18.0 j Sqdlfres almneetu Caster Piet tog i
l Cr115 0 wt 0 3406 0.0 16.1 14 41 45 l o-1 84-3 0 wt 0 3S00 0.0 8.1 13 30 51 f DC149 0 wt 0 0.0 19.7 24 40 36 CF35, O vt 41 3600 0.0 11.9 16 22 63 surlyb=3 153410 414350 o pwt Gs 614 2.3 0.5 10.0 30 36 34 l l Ter-1 704990 530320 0 et G1/Aa 404 0.2 41.0 1.S 13.0 12 32 56 Tar-4 105400 538410 0 ows vp S$4 0.5 15.0 1.3 9.0 20 31 49 CF 1.3De-S 719500 590540 0 pwt te/Ar 480 0.2 11.0 4.4 15.0 15 32 St Cr LSM-1 715350 $96000 0 aset $p/Gs $16 0. 4
- 14.0 2.S 11.0 24 39 30 i ausG2a-S 194060 549910 0 swt evy 462 3.7 15.0 22 39 39 susG2e-4 180130 $50240 0 pet avy 109 16.0 0.2 0.4 Il 42 40 esw G-1-2166 770$00 $61000 C b 8e 527 0.4 41.0 2.6 9.1 0 32 49 l Osw 4-1-2231.0 170500 $41000 C pet 3100 0.0 12.2 22 36 42 i ese G-1-2233 170500 $61000 C met te 500
- 2.2 20.0 0.4 15.0 32 24 42
- 034 t=1-2246.0 170500 341000 C pwt 3000 0.0 11.8 19 45 36 esw G-1-2241 170500 361000 C met te 500 3.4 16.0 0.4 12.0 32 29 39
- Wsw G-1-2209 170$00 $61000 C not te 500 1.4 15.0 1.0 14.0 13 29 St
- Tsw 8 1-2291 170300 561000 C nwt le 500 3.0 20.0 0.6 13.0 33 32 35
- I tsu G-1-2300.4 ??0500 561000 C pet 3150 0.0 13.6 24 31 45 esw G-1-2318 170500 S41000 C not SP/Gs 500 4.0 20.0 0.0 25.0 31 33 34
- Wsw 6-1-2354.6 770$00 S41000 C ows Gr 3750 0.0 14.4 27 30 43 Osw G-1-2363 110$00 $61000 C rwt sp/Cr 500 t.4 26.0 0.2 20.0 22 40 39*~
esu G-1-2397 110100 561000 C pet vp 3150 0.2 13.0 23 32 45 W3w G 1-2411 170500 $41000 C pwt sp/Gr 431 0.9 13.0 3.0 16.0 22 34 44
- 954 6-1-2436 770500 561000 C owt sp/Gr 500 0.0 39.0 0.6 10.0 12 39 49 '
\
l TABLE II (CONT'D.) La,n3.l e Blet tt e R kg kg f,3,,Il lie tahl.21 &ll.!.!L- Ltt u a me.e r BLfig A** tite tire *a A* ' 113 11111,1 tesfie- and neeeesere-estasral Caneeatratleae in rarte ser taillionT vsw 0 2-3159.4 0 0 0 0 1330 tr tr 0 ts tr Usu G 2-3216.7 670 0 0 0 0 0 tr 0 3 0 tr csw G 2 3244.4 600 0 0 600 0 to 3 tr 0 0 tr Osw tv-3 1571.7 te tr 0 22 tr 0 3 tr 0 tr Osw 59 3-1390.9 920 tr 0 1840 2160 0 tr ? tr 0 to tr i Usw sv.3 1603.2 130 0 0 030 tr 0 ' tr 0 tr
, Osw SU-3-1744:0 1605 0 0 tr 1605 0 o tr i Usw 0g-3-1873.8 tr tr tr 1 930 tr 0 930 1860 0 tr 0- tr Osw Gv 3 1986.3 se tr 0 1320 -1760 0 tr tr ?
0- te Osw G-f=2069.0 0 0 0 2000pe 1000 0 te 1 tr 0 tr tr 3 Osw S-4-2226.7 158 0 0 0 1915 0 0 0 > te s' De=25elt=1832.1 0 0 0 0 ,0 tr De-25 e 41 18 6 9.1 0 0 0 0
, y , 4 - 1 4-
'0 De-2Seft-1930.5 0 0 0 0 0
, 4 De=23 eft-2001.7 0 4
0 0 0 0 4 De=25 eft-2081.7 0 0 0 0 0 De=25e01-2113.6 0 0 0 0 0 4 De=25 eft-2220.6 0 0 0 0 0 4 De=23e41-2304.6 0 0 0 0 0 4 De=2Se41-2331.5 0 4 0 0 0 1 4 J-13-1682 1200 0 0 pe pe 0 0 0 0 22 34 J-13-1683 0 3100 0 pe 400 6 J-13 1992 5 6 Sm11f ree teamber. Croter Plat tuff Cr115 6000 0 1000 0 2000 tr 0-1 04 3 9000 0 0 0 1000 0 2 BC149 6000 0 2 0 0 0 0 C715, 14000 3000 2 0 0 3000 ,tr putyD-3 1900 0 0 0 540 0 2 0 0 0 10 - 26 6 T1r=1 3700 1300 0 0 4500 0 420 150 0 120 91 6 Tar-4 2700 2400 0 0 1000 0 0 440 0 130 11 Cr LSM* S 3600 290pe 0 0 1100 0 6 0 0 0 2t IS Cr LSd-1 1100 0 0 0 1500 0 0 6 0 0 15 Il SwC2a-S 4600 pe 0 1600 6 0 0 11pe. 0 0 19 41 6 asC2e-4 3400 pe 0 'O 1500 0 0 0 0 to 26 6 Orw G 1-2166 800 0 0 '0 930 0 0 0 0 0 13 6 Use G-1-2231.0 2700 1300ps 0 0 810 0 0 0 tr tr 6 , Osw a.1-2233 2700 tr 0 0 660 0 0 0 0 0 14 4 l Usw 6-1-2266.0 4300 1000pe 0- -0 1700 0 0 _0 0- 0' tr 6 tru o-1-2241 3290 0 0 0 1500 0 0 0 0 0 21 6 03v Cal-2289 2900 po 0 0 2200 0 0 0 0 0 26 6 Usw 0 1-2291 2000 pe 0 0 020 0 0 0 0 4 11 6 Usw 0-1-2300.4 1600 2400pe 0 0 1600 0 0 0 se tr 6 Orw s.1-2318 4200 0 0 0 2100 0 0 0 0 17 01 4 93W 0-1-2354.4 3500 2400ps 0 0 1900 0 .0 0 Osw G 1-2363 2500 pe tr - te d6 0 0 1700 0 0 0 0 45 40 6 gas g=1-2391 5300 1300pe 0 0 530 0 0 0 te to 6 Usw G 1*2411 2400 *pe 0 0 920 0 0 0 0 21 12 6 D8u G-1-2436 2900 pe 0 0 1000 0 0 0 0 54 43 6 l L h
TABLE II (CONT'D.) gg, a m geel Se$pte hoek A. Iter = Potate 11 Lie talgg Littles relate g Ag g g nat. Leag. M ZIES Allie.' Ceested Phem.I fposth) meet! Teltaa Passent of total hqgg 4 et relege Ebenocrystal grw 9 1-2441.5 170500 Sf1000 C ows vp 3650 0.9 7.1 5 44 $1 vsw G-1-2470.6 ??0500 Se4000 C put vp 3700 1.6 8.3 13 29 53 ysw e=1 2477 ??OS00 361000 C mwt sp/Cr 459 0.0 20.0 0.9 4.3 13 gyw u=1-2418.3 170500 361000 C 33 54
- rws vp 3750 0.5 10.0 14 35 47 psw G-1 2406 770500 $61000 C pwt As/sp SCO 0.0 17.0 S.2 9.6 6 52 42
- U2w G-1=2507 110S00 $61000 C met 3700 1.2 9.4 13 D8v G*1*2SSS 170500 341000 C p=t 36 St te 2515 0.6 15.0 2.3 11.C 7 45 44 vsw e=1-2SSS 170500 $61000 C n=t te 3S20 0.8 9.9 9 40 $1 etu 4=1 2$94.2 170500 561000 C pet 3750 2.2 1.1 17 32 $1 tsu 6 1-3601 170500 S61000 C rwt te 500 1.4 8.6 2.0 8.5 11 39 S0 e Usw 6-2-3292.5 770824 560504 C nwt le 1300 0.4 15.8 Il 31 '48 Osw 6-2-3294.0 178024 360504 C nwt 8e 1500 0.0 10.0 25 34 41 Osw S=2 3313.0 170824 360504 C pwt 1365 0.4 11.7 19 ' 34 47 Osw G-2 3326.9 170s24 S60$04 C ows 1430 0.3 14.4 18 42 40 use s=2-3i42.1 778426 S60504 C put 1500 0.7 10.1 18 45 40 gew '8-2-3 4 3 3.9 170824 S60504 C rwt 1500 0.0 10.3 1 42 51 Osw 09 3=2010.9 752690 358501 C 1530 <0.1 0.3 pew c0 3=2076.4 752690 558501 C to 31 49 1530 <0.1 10.9 17 31 46 vsw CU-3-2138.S 752490 554501 C 1630
<0.1 16.5 22 36 42 Usw GU-3-2181.4 142690 554501 C 1380 2.0 16.5 le 34 48
~
vsw ev=3 2369.6 152490 $$8501 C 1580 <0.1 , 10.3 to vsw wo 3=24 67.3152490 538501 31 43 C 1853 40.a 20.6 20 34 44 Wsw SU-3-2577.6 752690 358501 C 1460 3.0 0.3 gru 6-4 2354.9 765207 363082 C e-t
- 11 36 S3
$131 1.0 16.4 33 33 34 J-12-2132 149209 $79631 c 0.5 17.6 20 42 39 J.13-2135 14e209 !?9451 C put 8p 301 0.3 0.3 20.0 Ja13-2175 149209 $19651 C met Gr 310 0.0 24.0 24 35 41
- J-13 2183 749209 S196S1 C 0.0 11.4 ge=25e#1-2361.7 764900 S4bJSC 25 to 36 C wt Sp/Cr 326 1.5 17.0 0.0 12.0 pe.2Sef t=2419.7 764 900 568350 C es ap/Gr .304 0.7 4.4 0.0 17.0 De=25et1=24 91.3 744 900 566350 C wt sp/Cr 480 0.0 13.0 0.0 16.4 l Team tanwher. Caster Flat haff
( Rw18e=$ 897000 417440 0 b G1 506 22.0 19.0 1.4 awa yt>=1 12.0 30 36 32 182900 415190 o met te/Ar 497 3.6 0.0 12.0 34 31 35 awywe+5 807600 $0??40 0 out sp/Cr 487 04 12.0 24 40 36 Osw e=1-2641.5 170$00 $41000 C rwt te 500 3.8 12.0 1.6 14.0 12 32 36
- Usw G-1=2670.0 170540 561000 C rwt 3980 1.3 7.5 15 34 $1 tsu 6-1-2699 770500 S$3000 C pwt se 500 S.2 31.0 1.0 1.0 48 - 31 21
- Usw 6-1-2772.6 170500 461000 C pet 3803 2.1 10.2 29 34 37 i
Osw 5-1-2*90 170549 341000 C rwt sp/Cr $99 6.5 11.0 9.3 9.2 61 17 15
- Usw S=1-2051.7 170500 961000 C ==t 3900 4.5 13.6 41 ' 31 22 j Usw G-1-2854 170500 $61000 C Fws sp/Cr 441 3.4 31.0 2.0 12.0 65 26 9*
r l Ora 0 1=2869 770500 $61000 C ows sp/Cr 2023 3.6 23.0 4.4 14.0 40 35 25 Osw 3-1=2069 170500 S61000 C ows 3360 3.4 12.1 41 35 24 Stu S=1 2901 170500 561000 C set sp/G 500 1.4 10.0 2.0 15 0 $5 25 19
- Usw S 1-2931.4 1'GS00 561000 C mwt 4000 3.3 12.9 31 32 31 Use 6 1-2930 170500 561000 C set Am 425 0.5 35.0 1.9 l
11 0 43 34 19
- V3w G=1=3001 770500 561000 C evt As 500 6.4 16.0 S.4 15.0 45 30 2;
- Osw s=1-3013.9 170500 861000 C pet 3500 12.3 12.9 27 44 29 Osw s=1 3117 770500 $61000 C pet to SCO 4.6 12.0 21.0 12.0 68 13 19
- Osw 8 1 3192.0 170500 561000 C pet 3600 23.0 9.4 33 30 3' Osw e=1 3197 170500 561000 C s*ws Ie/py 2154 0.4 9.7 27.0 e.9 29 29 42
I TABLE II (CONT'D.) I
$4aple 31 state R M RE M M h h LMII Leit,le A8891% 9 D 84 f 6 met >e r Osta de e M i
. taa fle- and kenesserv-441aarel Caseentret t le perte ser 9111110n1 gre 6 1 2441.5 2200 1600pe 0 0 $50 0 0 0 tr tr csw G-1-2470.6 4900 1100pe 6 0 0 1300 0 0 0 te tr 6 Usw G-1-2417 2000 pe 0 0 1400 0 0 0 0 gpv g.1-2478.3 41 64 6 4000 S30pe 0 0 270 0 0 0 te tr 6 Ofw g-!=2406 2200 pe 0 0 1300 0 0 0 0 28 12 6 vsw 9-1-2507 4100 3200pe 0 0 2400 0 0- O Usw G-1-2555 1700 2300 0 0 . 420 0 tr tr '~ 6 0 0 0 33 usw G-1-2555 2300 2:00 260pe 0 200 32 6 0 0 'O t r 4 71 paw e-1-2594.2 4300 270pa 0 0 tr 6 800 0 tt 0 esw e-1-2601 19?0 pe 0 0 1100 0 0 tr tr 6
. 340 0 26 38 6 Osw 8 2-3292.S 6105 0 0 0 825 0 C' tr ' ' 3 '
tr Usw S-2-3294.0 4123 0 0 0 630 te 0 0 0 0 esw 6-2-3313.0 $820 - pe 0 0 744 ' tr
*33 0 0 '0' 'O Osw S-2-3326.0 4104 0 0 0 0 tr 0 0 0 0 Sfw 4-2-3362.1 1976 pe O C 729 0 tr .3 0 0 ,
O te '3 Ose 6-2-3433.9 2675 pe 0 0 1391 0 0 0 0 Otw 99-3 2018.9 2640 tr 0 0 2640 0 tr 3 Osw CU-3-2070.4 4640 tr 0 te tr ? 11650 0 0 1160 0 0 0 Orw 00-3 2138.S 7040 1760 0 0 1760 te te tr 7 ptu 69-3 2181.4 5250 tr 0 tr tr 7 1750 0 0, 3500 0 tr 0 te tr ? peu 90-3 2369.6 5790 tr 0 0 3860 tr tr 0-csw G0-3-2467.3 6510 4380 0 0 2190 te tr ? 0 tr 0 Osw 60-3 2577.6 3500 900 0 0 1000 tr te tr ? gre s-4 2354.9 4215 2223pe tr 0 te tr 7 0 3 171 0 0 J-13-2132 5000 0 te tr 3500 0 0 1500 3
, 5 J-13-213S J-13 217S 3700 0 0 0 1300 0 6
0 0 0 Ja13-2183 9300 3600 0 0 2500 54 34 6 De-25 eft.2261.7 $ De-2Sett=2419.7 4 4 De=2 Sal 1=2491.3
't Itas teaudge r, Cret e r F1.4t Tu f f Rutte-S 4000 9 0 0 170 0 0 99 4 ??
but W 1 4100 0 20 3 0 0 Sto 0 0 46 0 50 awome-S 3700 0 0 0 26 4 1400 0 0 310 0 Orw 0 1-2641.5 $700 120 to 6 0 0 0 2000 0 0 0 Osw G-1-2676.0 0 43 25 7300 0 0 0 1000 tr 6 tr 0 te tr 4 Trw G-1-2699 S200 0 0 0 1700 0 0 0 0 92 25 Osw E-1 2772.6 5800 1600pe 0 0 $30 0 0 0 Urw 6 1 2790 3000 0 0 0 630 0 tr tr 0 0 0 32 Orw 4 1 2951.7 4400 0 0 0 1810 0 20 4 0 0 Osw e 1=2854 3400 0 0 0 980 0 te tr 6 0 0 0, 46 39 . 6 Wsw 9-1-2069 4500 0 0 0 1000 0 0 0 0 Osw 6-1-2069 4000 0 0 73 4e 6 0 690 0 0 0 Osw 4 1-2901 3700 0 0 0 1100 0 tr 6 0 0 Osw S-1-2931.4 1000 0 0 0 500 0 , 10 9 6 0 0 0 Osw 6-1 2934 4300 0 0 0 1400 0 tr 4 0 0 0 09 41 6 Otw Gal 3001 3200 0 0 0 1900 0 0 0 0 4t U3w G.1 301) 9 4900 pe 0 0 040 0 63 4 tr 0 Utw 6 1 3117 1400 0 0 0 pe 0 0 tr 4 90 0 36 Osw G al=3192.0 4200 0 0 0 290 13 6 0 0 0 Usw G 1=3197 2500 0 0 0 22pe tr tr 6 0 0 0 0 13 6 6
\
l TABLF II (CONT'O.) ses,lo 1 stee l sam' ele secA alter- ** Late Inus tugs utute reAets g gg g m se t . s.eas . _trea l 22s titu' 3 C'***44 L!s' fnershi (Lastl l Tal m Pers.nt o f Tot al Rock l of Fele6e f _be noc rv e t ei WTv G-1-3197 170500 SS1000 C mwt 3440 22.3 7.4 30 esu 4 1 3258 110500 561000 29 33 C nwt te/ay 2151 0.0 9.1 20.0 10.0 32 33 33 esw 0 1-3254.5 770500 $61000 C pwt Ar/ec 3600 9.0 0.4 35 21 34 ptu G.1-3321 ??0500 $41000 C not ta/py 500
- 2.2 4.4 23.0 12.0 48 13 g3 e cru 4 1 3372 170500 %51000 C not ta/py SCO 0.0 1.6 37.0 6.4 43 36 2g .
yyu G-1-3501 710500 S61000 C Pvt to/py SCO 0.2 6.6 34.0 9.0 40 19 you G.1 3515.1 170$00 581000 42
- C p ut 3000 25.4 4.3 34 22 44 WSw G 2-3034 718824 $50504 C ta/Ar 2950 12.4 4.1 31 24 40 tsw G.3-2627.3 752100 S$1483 C 1630 1.0 0.6 20 16 64 ges 6*3*2656.s 752780 S$8483 C 1580 2.0 10.6 26 31 43 vvw G.3-2699.0 752700 558483 C 1630 4.0 12.2 29 25 46 pyw G=3 2133.0 752140 $$4463 C 1630 2.0 11.0 35 31 '32 gew 4 3 2801.4 752780 $$8483 C 154J <0.1 11.4 33 34 33 Wee G.S=2867.0 152700 558483 C 1630 2.0 9.4 33 33 33 ysw G-3 2 64 4. 6 7*2180 $58483 C 1640 3.0 14.4 38 33 29 gew G-3 3045.5 152700 $$4483 C 1680 13.0 12.1 30 32 30 see G-3-3072.3 152160 558493 C 1600 2.0 14.3 32 34 34 vsw G 3 3113.3 752160 $$4403 C 1655 14.0 14.4 38 27 35 gew G.3-3164.4 752780 550413 C 1500 20.0 13.1 29 32 39 tre D-3-3226.1 182700 550403 C 1600 18.0 11.9 36 37 28 yew 5-3-3343.0 152700 3S4443 C 1600 19.0 9.9 50 26 24 Upw 4-3-3441.0 152780 350483 C to80 28.0 10.S 38 24 36 opw G.3 3475.6 752700 558403 C 1530 25.0 7.S 24 25 St Osw G-3 3642.9 752700 558483 C 1630 34.0 0.4 49 15 35 peu 0-3-3730.5 752180 558483 C 1500 31.0 7.4 35 24 41 UTv G.3 37S9.2 752700 $l4483 C 1680 28.0 0.1 27 27 41 Osw G 4 2815.6 185807 S63012 C ows $074 14.2 10.4 38 29 34 De-2Syft-2340 756171 $11415 De 3.1 8.1 33 45 22 De=2SpJ1 2660 156111 $71485 De to.S 1.6 29 26 el De=25pf16'160 186171 571485 De 9.5 S.9 33 35 32 J-13-2302 749209 S196S1 C nwt sa 300 1.3 7.0 25 34 41
- i J.13 2382.S 749209 $19451 C 0.1 6.1 19 43 19 J-13 2532.1 149209 S194S1 C 0.9 9.6 28 39 33 Je13 2535 149209 S196$1 C wt la 300 1. 0 ' 11.3 l J 13 2600 149209 $19651 C wt sp 300 6.3 8.5 l
J.13 26 4 149209 5796S1 C 3.4 11.5 34 34 31 J-13 2685.2 149209 S79451 C 1.4 12.1 54 29 31 ! J.13-2043 149209 5796S1 C 0.0 13.7 38 34 28 J-13 2980 149209 $196S1 C ows sp/ce 300 5.3 13.0 J.13a2997 40 26 34
- 149209 579451 C vt sp/ac 300 1.1 10.0 9.0 J-13 2994 199209 $19451 C 13.5 7.7 *: 31 41 J-13*300S 149209 $196S1 C 4.4 7.9 34 29 31 J-13 3030 149209 S194S1 Db 7.0 12.4 41 21 32 J.11-3110 149209 5794S1 DD 2.0 4.8 20 $3 21 J-13*3150 149209 Sil651 Db 2.0 6.4 19 36 45 J-13 3190 149209 579451 Db 4.0 4.6 29 41 29 J-13 3200 149200 $194S1 Db 2.0 3.6 20 40 40 Raywesette plow stocene E3w G.1 3599 170$00 561000 C tb te/Q/es 500 0.0 11.0 0 0 100
- Csu 4 1-34S9 110500 561000 C tb At 300 0.0 11.0 0 0 100
- Dsu G-1-3106 ??0500 561000 C tb Sc/0 SCO 0.0 10.0 0 0 100
- Esw G=1 3724.0 170500 SE1000 C ft 41/0 3700 0.0 0.0 0 0 100 Csu G-1 3tSO 170500 561000 C tb 8e/0/Ae SCO 0.0 11.0 0 0 100
- TABLE II (CONT'D.)
p.a.1. aana a mi as run ne n!nas mu-1***** zw- wo num m' m BMs1 ha Ite f te- and &acesserv-esimere! C~menet rot tene le Pa rt e ser te.111ted tyw 6-1*3197 3200 0 0 0 200 0 0 0 tritt ge g Orw 6-1*3250 2300 0 0 0 16ps 0 0 64 0 18 13 USw 8 1=3204.5 3300 pe 0 0 1700 0 tr 6 gyw s-1 3321 0 . te tr 4 2500 0 0 0 250ps 0 0 100 0 22 esw s.1=3372 1900 0 0 0 pe 0 0 30 'd
$ 6 3 2 4 Osw s-1-3501 1500 0 0 0 pe 0 0 120 0 28 Osw S*1 3515.1 2900 260pa 0 0 1300 0 3 4 gyw 5-2.'3834 tr 0 tr tr 4
??4 2Sepe 0 0 114 tr 0 0 0 vsw e-3-2427.3 7520 410 0 0 410 te tr 0 tr 3 te Usw 6 3 2436.0 4140 0 0 0 te tr tr ?
tr 0 tr tr .1 vsw 6-3*2699.0 2520 0 0 0 430 tr 0 0 tr te 2 vsw e-3-2133.0 5900 0 0 0 2360 0 0 0 gav G-1 2801.6 te tr 7 1340 tr 0 0 te tt 0 0 te tr vsw 5-3-2087.0 6060 tr 0 0 1010 0 tr 1 0 te to 1 91w G-3-2914.6 9300 tr 0 0 1350 te tr 0 te te i vpu e-3-3045.$ 1920 0 0 0 2640 0 0 0 tr tr Usw 0-3-3072.3 6000 tr 0 0 3040 tr 0 0 i te tr ? Usw 0-3 3113.3 4500 150 0 0 750 0 vsw e-3 3164.4 2760 tr 0 0 0 te sr 1 0 4140 0 0 0 tr pas e-3-3226.1 1920 640 tr 1 0 0 3a60 0 0 0 te tr ? Osw c-3 3343.8 4400 0 0 C. 3340 0 0 0 te is 1 vaw 4 3 3141.0 2200 0 0 0 3300 tr 0 gew 0-3 3415.6 0 tr tr 1 4300 tr 0 0 4800 tr 0 0 te tr 1 Osw 9-3-3642.9 $$20 0 0 0 2T40 0 0 0 tr tr 1 saw G-3 3130.5 4000 0 0 0 1600 0 0 0 tr tr ? Tru G-3-3759.2 4500 990 0 0 3600 tr 0 0 0 tr 1 Osw 6-4 2815.6 6327 222pe 0 0 555 0 0 0 tr te De-25p41-2300 41$ 0 0 0 1909 0 0 3 0 tr De=25p41 3640 3001 405pe 0 0 405 0 3
< 0 te De 25p41-2760 3168 0 0 0 4224 0 0 3
0 te 1 J-13*2302 4000 0 0 0 2400 'O 33 0 0 130 49 J-13 2342.5 4300 800 0 0 000 6 J 11 2532.1 9300 600 0 0 600 5 J 13 2535 $ j J=13=2680 4 ! 6 l J-13 2684 6400 900 0 0 900 t J-13-2405.2 10000 700 0 0 10000 5 J-13 2043 8600 2700 0 0 600 5 J-13 2900 3500 0 0 0 1900 0 0 0 0 13 42 J-13-2997 4 4 l J.13 2998 000 600 0 0 600 J 13-3005 4500 0 0 0 1300 5 ] J-13 3030- 3900 0 0 0 2600 5 i J 13 3110 900 0 0 0 0 g J-13=3150 2100 0 0 0 9 5 3 J-13 3190 4000 0 0 0 0 J-13-3200 2000 0 0 0 1500 3
' .s:
DJoyedeelte Flow trocate Utw o-1-3590 0 2300 1200 pe 2300 0 0 0 0 440 Orw G-1 3459 0 9500 2700 11300 4500 0 0 0 6 0 0 1300 U3w 4-1 3106 0 1100pe ye yo 2300 0 0 4 0 0 0 1700 Uru G-1-3124.0 0 11100 15100pa 0 4100 0 0 6 0 0 l Osw G-1-3tl0 1 2400pe 230pe ye 3200 0 0 tr 0 4 0 0 460 0 6 I l 19 -
TABLE II (CONT'D.) s ,te s steel seht. ame us e r- e.1sts '.21k tunits utues relate g g g per 146. & meg. Mh3 m i C m ted Phen I (peML(As ati v.1-e res es ertuta n.a e ee reisse fhonocrystel j Tsw e.1 3900.2 ??0iOO S41000 C tb C1 3130 0.0 10.0 0 0 100 gsw G-2 4134.2 774824 560504 C ib 2400 0.0 19.1 0 0 100 M S u t M ese h ff awome.4 001600 $05010 o not Ar 467 8.3 4.3 19.0 6.6 3 39 St Twe-475 079468 609999 C pwt 8c S13 S.8 S.6 S.2 0 45 SS Tsv 4114 02 801940 $93430 0 p*, Si te.s e 409 4.8 11.1 3.1 4.6 4 32 44 rette-l 021930 631480 0 not te 199* S.3 2.3 3.0 0 21 10 ! paw 0 3h1 170500 $41000 C b At 199 0.3 17.0 6.0 15.0 0 0 100
- Tsu g-1.?t49.9 170500 $61000 C owt At 3300 9.0 17.1 2 34 '44 Usw G-1=3992 170500 561000 C pwt 3500 26.1 11.3 4 31 65 vsw 4 1 3991 170500 561000 C nwt le 311 4.0 6.9 13.0 13.0 6 $8 36
- Usw S-1*4005 110500 S41240 C net to 897 1.1
- 9.8 26.0 10.0 2 el 5)
- sse' 0-1=4130.4 170500 561000 C twt 3400 13.8 8.5 2 Jt 43 Usw 6 1 4300 770500 541001 C not , se 610 0.0 6.2 39.0 9.5 0 71 29
- Usw 6 1 4222.1 170300 $4 06J C res 3200 42.7 6.1 7 40 S3 Orw G4!=4296 ??0500 SS1000 C nwt 2e 615 C.9 8.6 19.0 12.0 t 10 22
- 4J 6-4 4342 170500 $41000 C not A3/te $57
- 0. 4 10.0 10.0 13.0 1 3S $4
- Use 8 1 4401 110500 $61001 C evt , Se/Aa 540 1.1 9.3 11.6 10.0 1 61 32 *
. Osw s 1 4400.4 770500 561000 C pet 1000 11.8 9.2 1 31 62 Usw 6-1*4471.0 170500 561000 C pet 3600 26.4 S.1 1 36 St 98w 6-1=4504 170500 S41000 C not to 629 1.3 11.0 20.0 0.2 S 64 20
- Usw G.1*4570.2 170$00 541000 C put 3500 23.8 7.6 S 39 56 ;
paw t-1-4612 770500 $41000 C nwt to 650 0.0 6.6 30.0 9.0 3 41 49
- Use 9-1-4700 170500 $61000 C pwt se $19 4.8 17.0 19.0 1.1 10 35 SS
- Usw S-1=4750.4 170500 561000 C pwt 3900 19.0 9.2 9 30 33 93u s=1-4805 170300 Se1000 C pet se 601 0.0 10.0 19.0 43.0 1 44 $$
- Osw 6-1 4949.0 ??0500 $61000 C pwt 3900 13.0 8.9 to 35 SS paw 6-1=4477
- 170$00 $41000 C fvs to/ec 454 0.3 11.0 11.0 8.4 6 SO 44
- U3w G-1 4913 170500 141000 C pet to $53 0.0 13.0 9.6 6.9 12 So 38
- Usw G=1 4917.0 710$00 S41000 C net 3000 S.9 S.6 14 51 35 Osw O-2-4199 170834 $40504 C m 1900 4.7 15.2 0 0 100 gru G-2-4267 170824 S40504 C nwt 1950 T.8 10.9 4 35 61 Was 6 2 4467 174824 $60504 C net 1900 11.2 8.5 10 29 62 V7s 0 3 3003.3 152100 S50493 C 1560 3.0 18.0 2 16 42 Osw 8 3=4006.6 752160 $50403 C 2600 16.0 10.2 2 al 13 T;w 4-3-4039.17 752700 554403 C 1500 10.0 7.6 0 33 59 isu 6 3 4149.4 152?lo 554s03 C 1630 16.0 1.3 12 33 SS ess G..'*4240.7 152100 $$8403 C 1200 25.0 1.5 11 34 SS s
vow 4 3 43?0.8 152700 550403 C 1430 28.0 10.2 S 49 46 Wes 6 a3*438 6 3 182700 $l8483 C 1500 21.0 9.1 6 40 54 trw S=3 4423.h 752700 558403 C 1630 17.0 8.9 4 48 of pse e.l.4430.4 152100 558483 C 1630 30.0 S.9 6 30 54 Osw 6 5-4564.1 761100 $54403 C 1531 20.0 11.2 4 35 to vsw 4 3 4689.1 152700 558403 C 1600 20.0 $.S 10 39 $1 tsw 6 3 4109.0 152100 $58493 C 1450 22.0 9.4 8 31 SS USw 6-3-4136.9 152700 554443 C 1630 23.0 15.0 1 29 44 Urw s-3*4839.4 152100 S$4483 C 1855 15.0 9.4 11 29 El Da=25p01+2950 754111 571493 De 13.3 6.1 4 15 41 l
TABLE II (CONT'D.) nea! 01a n s a as as ren un mm mm rm: muumm nu.' ESLI 9 EMS.t L(t AidM g,(le- and heeerv-441aeral caneestrat taes in Part s mer es111 Lea l esw 0 1 3908.2 0 1900 2500 8200pe 5700 0 0 0 tt 0 6 saw s 2 4134.2 15435 94185 1260 0 6300 0 0 0 tr tr 3 L&tlhas &&ees futf sewwwe-4 1600 0 0 0 590 0 0 0 0 26 24 6 Tws.479 1000 1000 f 0 180 120 140 0 48 54 34 3-tsv.417A*82 490 1400 130 26 620 31 190 0 3 $9 19 3 rs16e=8 1340 85 0 0 1190 6 693 0 0 12 23 3 vse s.1 3941 3200 600 0 0 pe 0 9 0 1 29 3 4 Tsw 4 1=3949.9 1500 pe 0 0 3400 te tr 0 te tr 6 esw 4 1*3992 9100 0 0 0 2000 te tr 0 te er 6 esw 4 1-3991 5400 0 0 0 2400 0 230 0 3 110 66 ** 6 vsw 8=1*4015 1100 0 0 0 1200 0 206 110 4 22 It '6 884 4 1 4160.4 1200 0 0 0 600 te tr, O tr tr 6 vow e*1=4208 1900 0 0 0 1100 0 200 180 0 $4 28 4 Wsw 4 1-4222.1 1600 0 0 0 1600 tr 0 0 te tr 4 Wsw S.1 4296 1600 0 0 0 1500 0 84 20 6 44 23 6 Wsw 6-1 4342 1900 0 0 0 1600 0 190 66 3 65 64 6 psu 6.!*4401 1000 0 0 0 1000 0 30 15 2 110 66 6 Tsw S-1*4400.4 5000 0 0 0 1100 te tr 0 tr tr 6 vsw 4 1-4411.0 3500 0 0 0 560 te tr 0 tr tr 6 Few 6 1-4504 2900 0 0 0 1600 0 0 0 0 16 31 6 gew S.1=4510.2 2600 0 0 0 $30 te tr 0 te tr 6 som S-1-4612 2000 0 0 0 1100 0 0 43 0 45 4 6 vsw 6 1 4700 1800 0 0 0 000 0 0 0 0 40 13 6 Usw e-1=4750.4 2600 0 0 0 1500 tr 0 0 tr tr 6 tsw G-lattel 3000 0 0 0 1400 0 0 59 0 43 45 4 USw 4-1*4149.0 3300 0 0 0 1000 tr 0 0 tr tr 6 esu s.1=4817 2100 0 0 0 130 0 0 14 0 13 26 6 93v s.1 4913 1000 0 0 0 1000 0 0 0 0 40 21 6 tsu 6 1 4917.0 3200 0 0 0 1000 te tr 0 tr tr 6 Usw 4 2 4199 8366 13172pe 0 0 ello 0 0 0 te tr 3 vsw G-2-4261 3955 0 0 0 1830 tr 0 0 0 tr 3 Tsw 4 2e4461 1968 0 0 0 3204 tr 0 0 te tr 3 l WSW 0 3 2003.3 26600 4400 2200 0 6600 to tr 0 tr tr 7 I ese 6-3-4000.6 8050 1150 0- 0 3450 to tr o tr tr 7 Use 6-3*4031.17 3400 1700 0 0 3400 te tr 0 tr - tr -? Use 0=l*4149.8 3200 0 0 0 4000 te tr O tr
- tr . 1 Wsw G-3*4240.1 2400 0 0 0 2600 tr tr 0 ta tr 1 tsu G-3 4209.6 1960 0 0 0 1190 te tr 0 tr tr 1 trw 4 3 4304.3 3920 0 0 0 2940 te tr 0 te te 1 tsu 8-3-4423.2 3040 0 0 0 1920 te tr 0 tr tr ?
erw 0 3 4431.4 3960 0 0 0 1990 tr tr 0 te tr .1 Usw 6*J 4566.7 2240 0 0 0 1120 te tr 0 tr tr 1 a "' ~ Usw S-3-4619.1 1160 0 0 000 te tr 0 tr' tr ? 93W 4 3*4709.0 3940 0 0 0 990 tt 0 0 , tr tr 7 tsu m.3 4136.9 3110 ,0 0 0 SISO te tr 0 te tr ? Osw 4 3 4t39.4 3000 0 0 c 3000 tr tt 0 tr te T Ue-25ptl 2930 3114 0 0 0 2514 440 220 0 tr 3 M_!
1 TABLE II (CONT'D.) see,la See alent manyte noen a. iter- potaa e mv enlee Liskies retene g g g m s.es . S.ne ,. 122s, 2 g3,3 3 tilta' C*** * *4 9"*a ' (Beath) (Beeti Teltem paresat of Tot al teeJt t of telete E be nec n e t eS De-2Sp41 3453.3 156171 571405 C 11.7 3.9 3 20 11 J+13-3244 149209 S194$1 C t.7 8.8 3 23 15 J-13-3251 749209 S19451 C 4.4 11.5 1 16 43 J.13=3253 149209 S19451 C nwt 2 301 12.0 12.0 J 13-3290 749209 S19451 Db 5.0 13.9 1 19 40 J-13-3450 149209 $196S1 Db 23.0 10.6 4 41 St Ja13-3491 149209 5794S1 C 13.4 9.4 S 31 64 J 13-3493 749209 S19451 C not te/sc 300 1.1 11.0 12.0 4 46 49
- J-13-3497 149209 $19451 C 10.8 4.6 4 34 St Older Tuf f a = 9mit & '
tre 6-1 4946.4 770500 561000 C met 3480 4.4 9.8 to St ' 22 Osw S.1 4 94 9. 0 7'10$00 541000 C pet 3700 3.1 11.9 24 31 45 vsw 6-1=4990 110$00 561000 C b A /2/84 4S? 4.4 18.0 4.2 20.0 37 31 32
- Ofw G-1-$002.3 170$00 $41000 C nwt 3700 2.5 17.0 32 31 37 esu O-1 5026 170500 841000 C p=t u 480 0.0 22.0 1.s 16.0 34 40 24
- Tyv e-1 5045.0 170500 561000 C ows 3700 8.9 19.9 ft 43 29 gru 6-!*S094 110$00 S41000 C h/ta p-t $46 0.2 28.0 2.0 13.0 49 19 32
- csw G-1=8091.9 710500 $61000 C o=t 3600 0.5 17.4 28 41 31 gru G-1*8113.3 710$00 561000 C ==t 3150 3.1 10.3 24 42 34 Wsw G-1=5121 'P70500 861000 C pwt sa 632 0.0 19.0 3.5 23.0 29 33 30
- Usw 0-1-5141.5 190500 S41000 C owt 1100 9.2 14.1 27 33 to Use s 1 8142.2 190$00 341000 C pet 3?SO 2.2 19.4 29 36 34 Osw s.t $161 170500 $41000 C not 8a/u /ce 488 0.5 14.0 15.0 10.0 ft 42 36
- tsw G-1-5107.0 ??0$00 $41000 C not 3150 2.1 17.6 to 30 30 csw e.1=S213 170500 $61000 C rwt sa $11 0.0 21.0 1.5 21.0 39 36 25
- Ute G.1 5288.6 ??0S00 $41000 C p=5 3400 S.4 11.4 35 31 34 Osu Gal *S294 170$00 $41000 C p=t t a /2 $84 1.0 32.0 2.? 19.0 23 SS 22
- Usw 6 1 5312 110500 561000 C b utte 424 0.3 14.0 3.0 14.0 35 46 19
- Cst G-1-5316.0 110$00 541000 C
- 3600 2.4 21.4 33 34 31 gru G 3-4906.5 182180 l$4483 C 1640 2.0 17.9 l
29 34 31 Tsw G-3=5014.( 752180 558483 C 1680 2.0 15.2 De-2Sp41 3570 754171 571405 De 30 35 38 co-2fp41 3600 756171 $7140$ 1.2 15.0 32 30 37 De l 1.9 11.S 21 39 41 Older Tuf f e = Dalt a con e-1 8349 710$00 $61000 C b 2/es 421 0.0 22.0 20.0 St.0 13 16 11
- Oru s.1*S3?3.7 ??0$00 541000 C pet 1450 0.6 11.3 l
Utw 6 1=S400.0 770500 561000 C pwt 13 24 61 3000 2.3 13.4 ! Osw G-1 5413 170500 861000 C pet ta/2 12 30 St I 410 0.2 14.0 11.0 11.0 44 4e* Usw e-1-8416.6 770500 541000 C pwt 3700 12.8 11.2 8 l la 27 42 l l 914er Tufte = Omit C Usw S.1=$438.2 710500 561000 C put 3900 0.1 trw g.1-8454.1 ??0$00 341000 C b 12.9 1 3 94 3801 1.9 14.9 10 66 934 6-1*S494.1 110$00 $41000 C put 3t00 le 1.5 10.1 95 Osw G-1=S498 770500 $61000 C pwt t a /2 422 0.3 25.0 4.5 1 4 Usw 4-1-S$17.3 770500 561000 C pwt 14.0 0 e 92
- 3400 10.3 11.0 2 9 89 l
7V
TABLE II (CONT'D.) aww1 s!.tSt. a mm 33 gs-n De tetsu h terr- m stre*a E 8 entit RL!!Lt 111 1.11h1 aantie- and &eeee eer,-eune ret come..t ret teae la te rs e ser an1111.m' so-23p41-3453.3 224) 0 0 0 3105 $20 0 0 3 J-13 3246 600 1100 0 0 2600 g J-13 3251 4000 tr 0 0 5000 3 J 13 3233 6 J-13=3290 tr tr 0 0 tr 3 J-13-3450 2200 0 0 0 2000 $ J-13 3491 4900 0 0 0 600 $ J-13 3493 2200 0 0 0 1900 0 0 260 0 65 40 6 4-13 3491 It00 0 0 0 1800 $ padar Tmffe Te4t & , , , , .. Wsw 4-1*4946.4 3000 0 0 0 300 tr tr 0 . tr 6 Wsur 4-1=4 96 9.0 4900 0 0 0 2700 tr 0 0 tr tr 6 see 6-1*4990 4000 0 0 0 1500 0 0 210 0 100 84 6 geur 6-1 5002.3 S100 0 0 0 2400 tr tr 0 te tr 6 yse c.1 5026 2200 0 0 0 1600 0 0 0 0 14 31 6 Tsw 6*1 5045.0 4100 0 0 0 1900 tr 0 0 ta tr 6 tw 5 1 1094 1700 4 0 0 1000 1 0 44 0 84 84 6 vsw 4 1-5097.9 2200 0 0 0 2000 te tr 0 tr tr 4 Use s.t.5113.5 4000 0 0 0 1900 te tr 0 tr tr 6 Ose e=1=S127 2300 0 0 0 2300 0 62 140 0 110 42 4 vow G-1=5141.3 2100 0 0 0 1200 tr tr 0 tr tr 4 vse 6-1=5142.2 3?00 210 0 0 1900 tr tr 0 to tr 4 tre 0+1-5167 800 130 0 0 2000 0 200 210 0 100 al 6 vse 6-1 5147.0 1600 270 0 0 2200 ta tr 0 tr tr 6 Usw 4-1-$213 2300 16 0 0 2400 0 51 210 0 100 el 6 vsw S-1 $245.6 2400 590 0 0 1900 te tr 0 to tr 6 vsw 4-1*5296 2400 030 0 0 2400 0 210 130 0 44 $? 6 Usw s-1 5312 940 0 0 0 1800 0 88 64 0 32 11 6 Use 6-1-$316.0 1400 0 0 0 2000 te tr 0 tr tr 6 Osw O-3-4 906.5 3660 0 0 0 1930 0 tr 0 te tr 1 Tsu 4-3-5014.6 6400 t 0 0 3240 0 tr o tr tr i re-25,41-3510 3220 0 0 0 to 0 0 tr 3 De=2Sp41 3400 1700 0 0 0 1824 0 0 0 tr 3 G&det .?tif.f_991t_9 - Osw S-1*l349 1000 0 0 0 3300 0 65 46 0 100 20 4 Use e 1-5313.1 0000 0 0 0 3300 tr tr 0 te tr 4 Use e.1.$400.0 4500 0 0 0 3200 te tr 0 tr tr 4 Usw G 1-3413 5600 0 0 0 2200 0 110 130 42 130 11 6 Saur 6-1 5416.6 2?00 0 0 0 3200 tr tr 0 te tr 6 G& der Tuff 4 9 tit C Osw S-1 5430.2 12000 0 0 0 4600 0 t r (?) O tr tr 4 Dew G=1=l454.1 7100 0 0 0 5000 ** t e t ?) O tr tr 6 Osw 6 1=5496.1 21100 0 0 0 4900 ra ta t?) O tr 4 tr 99w 0 1 5490 $400 0 0 0 3100 0 41 160 0 210 ft 6 Das Galall17.3 11400 0 0 0 4500 te ts (?) O te tr 6 I e0
TABLE !! (CONT'D.) Semple seesttenI le beeA A.1ter. Petsta 1219. M hA.I.I.112 Falste g A_r g Note t &et. &amt. M IXE1I 111*** M 'd '"**' f ue et n t (se e s t vel- Peteent o f Tot a l neo e et rel te ene neerretel Urw G*1'll40.0 110500 141000 C pwt 3900 0.5 13.5 1 0 99 caw 6*1*llte.1 110500 841000 C pet 3600 0.4 19.1 4 4 92 Usw 4*1*l400.0 ??OSCO 141000 C owt 3150 8.4 14.4 5 1 33 csw 4*1-561? 110500 541000 C est te/Aa/es 439 0.1 4.4 S.8 14.0 0 3 35
- Use 0 1-5842.0 ??0500 541000 C ows 3300 S.4 16.4 2 4 $4 ese s*1*lete 710500 541000 C b se 440 0.3 23.0 S.9 20.0 0 2 54
- rsw 4=1-5728.0 170500 541000 C met 1450 21.1 21.4 0 Osw g*1 5147 1 59 770500 141000 C put se/Ab 543 1.4 10.0 4.3 27.0 0 0 100
- Usw G*1 9041.0 ??0500 841000 C ows 1450 10.4 18.0 0 4 le Osw 6-1=S84s ??0$00 541000 C put Am 42? 0.0 15.0 20.0 23.0 0 10 to e Osw s.1=5094.3 190500 S41000 C ows 1830 1.2 15.5 0 4 . 14 Osw s*1*S329,8 ??C500 341000 C met tele 5.9 18.2 4 4 92 Usw 0 1*S944.9 170500 541000 C ows 1400 6.3 21.4 1 4 91 Urw 0-1*5948 ??0$00 581000 C pet to/Ab 434 0.0 13.0 4.2 23.0 0 12 48
- Usw 6-1*$300.0 110$00 541000 C ows 1450 3.3 20.9 0 1 99 vsw e*1=Spet.1 170500 $41000 C ows 1450 2.3 25.3 0 0 100 Usw G*2 4838 170424 540504 C put 1850 1.5 14.0 Usw G-2 4824 118824 540504 C 1 3 94 1 1000 0.0 S.4 0 0 100 Usw 6 2*l011 178024 S40504 C 1 1800 0.0 De.2 Spit =3440 1.4 0 10 90 154171 $71405 De
- 1.0 14.4 1 8 94 De=26pf1=3470 154111 Sitet$ De
- 10.5 14.0 1 2 97 De*2Sp41-3130 754111 571405 De t.0 11.4 0 2 ft
1 l l TABLE II (CONT'D.) l awet e tin 11La R Ses 9ta Lt-IA 1ha Athia.1 AM.ta: F.tu.: Aosttie liite tiL' Estt11 SE112.1 111 1111.t tan tie- and seeeeeerv eaineral emeeentratleae in part e ser talition' cpv s.1 1540.0 19200 910pe 0 0 43?0 tr 0 0 te tr 4 08u 0=1'1558.7 16400 1100pe 0 0 530% te t:(?) 0 te tr 6 Osu 6 1=5600.0 10100 400pe 0 0 4400 tr trt?) O tr t: 6 Osu 0*1-8431 10500 pe 0 0 4100 9 110 45 0 280 56 6 Osu 4*1 5642.0 21$00 1800pe 0 0 8000 ts t e (?l 0 tr tr 6 Oss 6-1=5400 3800 410pe 0 0 3000 0 200 410 0 200 64 6 Osu 4 1 3124.0 10200 pe 0 0 1900 tr ta t ti 0 te to 6 Osu 0 1*S141 9900 0 0 0 55 65 0 t Upv 0 1 5641.0 12100 600pe- 0 0 9500 te t e tti 0 tr .tr 6 Use 6 1*5048 6200 0 0 0 4100 0 to il 0 210 96 6 gre 0 1 3094.3 6100 6100 0 0 3600 te tetti e tr te 1 Osu 0-1*S929.0 13300 5500pe 0 0 4100 te tritt O te gsu 0-1*$944.9 te t 6900 1500pe se 0 5000 te setti 0 tr tr 6 tsu 0 1*5948 5200 3 40p s 0 0 6100 0 0 0 300 10 50 6 Usw 0 1*l900.0 I(200 7300pe 1800pe 0 7300 te te(?) 0 gr t 6 9pv 4 1 1944.7 27200 0$00pe 1200ps 0 9100 te te(?) 0 te css 0 2 4834 10269 0 0 0 4890 tr 4 tr 0 0 tr Osw 4-2=4924 11400 3000pe 0 0 3040 te 3 0 tet?) O te 9pv 0 2 1017 9310pe 0 0 0 tr 3 1140 tr 0 0 te pe.25 pit 3640 14645 0 0 0 4600 tr 3 0 0 0- O te 3 De-25p41 3610 10676 172*pe 0 0 4553 0
- 0 0 0 tr pe.2Spil 3130 1403? 263tpe 0 0 8323 0 3
t 0 0 te 3 s
& h gf g 49 *- # '
h
List of Figures 1. Map of Yucca Mountain, Nevada, showing the locadons of drill holes discussed in the text. 2. Summary of petrographic data for the Older Tuff Units A, B, and C at Yucca Mountain, Nevada. (a) Histograms showing distribution of total phenocryst abundances. (b) Triangula diagram showing the proportions of quartz (Qtz), sanidine (San), and plagioclase (Plag) phenocrysts. There are no data for outcrop samples. (c) Histograms showing the distributjon of Or + Cn (onhoclasse and celsian)in sanidine, An (anorthite)in plagioclase, and Mg in biotite phenocrysts for Older Tuffs Units A, B and C at Yucca Mountain, Nevada. Number of samples equals thin sections probed; number of analyses equals the number of chemical determinations performed. Shaded areas of histograrns for plagioclase phenocryst compositions indicate rim compositions; unshaded areas indicate cores, midzones, and rims undivided. There are no data for outcrop samples. 3. Summary of petrographic data for the Lithic Ridge Tuff at Yucca Mountain, Nevada. (a) Histograms showmg distribution of total phenocryst abundances. (b) Triangular diagram showing the proportions of quartz (Qtz), sanidine (San), and plagioclase (Plag) phenocrysts (c) Histograms showing the distribution of Or
- Cn in sanidMe, An in plagioclue, and Mg; in biotite phenocrysts fer the Lithic Ridge Tuff at Yucca Mountain, Nevada. Shaded areas of histograms for plagioclas phenocryst compositions indicate rim compositions; unshaded areas indicate cores, midzones, and rims undivided.
4. Summary of petrographic data for the Tram Member of the Crater Flat Tuff at Yucca Mountain, Nevada. (s) Histograms showing distribution of total phenocryst abundances. (b) Triangular diagram showing the proportions of quartz (Qtz), sanidine (San), and plagioclase (Plag) phenocrysts. Jc) 'fistograms showing the distribution of Or + Cn in sanidine, An in plagioclase, and Mg in biotite phenocrysts for the Tram Member of the Crater Flat Tuff at Yucca Mountain, Nevada. Snaded areas of histograms for plagioclase phenocryst compositions indier.te rim compositions; unshaded areas indicate cores, midzones, and rims undivided. 5. Summary of petrographic data for the Bullfrog Member of the Crater Rat Tuff at Yucca Mountain, Nevada. (a) Histograms showing distribution of total phenocryst abundances. (b) Triangular diagram showing the proportions of quartz (Qtz), sanidine (San), and plagioclase i (Plag) phenocrysts. , plagioclase, and inMg,(c) Histogr ms showing the distribution of Or + Cn in sanidine biotite phenocrysts for the Bullfrog Member of the Crater Flat Tuff at Yucca Mountain, Nevada. Shaded areas of histograms for plagioclase phenocryst compositions indicate rim compositions; unshaded areas indicate cores, r/41mes, and rims undivided. 6. Summary of petrographic data for the Prow Pass Member of the Crater Flat Tuff at Yucca Mountain, Nevada. (a) Histograms showing distribution of total phenocryst abundances. (b) l > Triangular diagram showing the proportions of quartz (Qtz), sanidine (San), and plagioclase (Plag) phenocrysts. plagioclase, and Mg(c) Histograms showing the distribution of Or + Cn in sanidine, in biotite phenocrysts for the Prow Pass Member of the Crater Rat Tuff at Yucca Mountain, Nevada. Shaded areas of histograms for plagioclase phenocryst compositions indicate rim compositions; unshaded areas indicate cores, midtones, and rims undivided. 22 l - t
I a
- 7. Summary of petrographic data for the tuffaceous beds of Calico Hills at Yucca Mountain. !
Nevada. (a) Histograms showing distribution of total phenocryst abundances. (b) Triangular ! diagrarns showing the proportions of quaru (Qtz), sarddir.e (San), and plagioclase (Plag) phenocrysts in the phenocryst. poor (<5% crystals) and phenocryst rich (>5% crystals) subunits, and Mg . in biotite phenocrysts for the tuffaceous beds of Calico Hills at Yu; Nevada. Shaded areas of histograms for plagioclase phenocryst compositions indicate nm : compositions; unshaded areas indi: ate cores, midzones, and rims undivided. Dua for .i phenocryst poor and phenocryst. rich subunits are not differentiated.
- 8. Summary of petrographic data for the Topopah Spring Member of the Paintbrush Tuff at Yucca Mountain, Nevada. Data for rhyolitic and quartz latitic tuffs shown sepeately. (a)
Histograms showing disuibutior, of total phenocryst abundances. (b) Triangular diagrams showing the proportionr of quar 2 (Qtz), sanidine (San), and plagioclase (Plag) phenocrysts (c) Histograms showing tN disvibution of Or + Cn in sarddne. An in plagioclase, and Mg; in biotite phenocrysts for orill nole samples of the rhyolitic portion of the Topopah Spring Member of the Paintbrush Tuff at Yucca Mountain, Nevada. Shaded areas of histogram for plagioclase phenocryst comyositions indicate rim compositions; unshaded areas indicate cores, midzones, and rims undivided. There are no data for outcrop samples ,(d) Histograms showing the distribution of Or
- Cn in sanidine, An in plagieclase, and Mg in biotite phenocrysts for the quartz latitic portion of the Topopah Spring Member of the Paintbrush Tuff at Yucca Mountain, N6vada. Shaded areas of histograms for plagioclase phenocryst compositions indicate rim compositions; unshaded areas indicate cores, midzones, and rims undivided.
- 9. Summary of pecographic data for the Pah Canyon Member of the Paimbmsh Tuff at Yucca Mountain, Nevada. (a) Histograms showing distribution of total phenocryst abumiances. (b)
Triangular diagram showing the proponions of quartz (Qtz), sanidine (San), and plagioclase (Plag) phenocrysts. (c Histograms showing the distribution of Or + Cn in sanidine, An in plagioclase, and Mg,)in biotite phenocrysts for drill hole samples of the Pah Member of the Paintbrush Tuff at Yucca Mountain, Nevada. Cores, midzones, and rims are undivided in the histogram for plagioclase. Dere are no data for outcrop samples.
- 10. Histograms showing the distribution of Or + Cn in sanidine, An in plagioclase, and Mg* in biotite phenocrysts for drill hole samples of the Yucca Mountain Member of the Paintbtush Tuff at Yucca Mountain. Nevada. Cores, midzones, and rims are undivided in the histogram for plagioclase, here are no data for outcrop samples.
- 11. Summary of petrographic data for the Tiva Canyon Member of the Paintbrush Tuff at Yucca Mountain, Nevada. Data for rhyolitic and quartz latitic tuffs shown separately. (a)
Histograrns showing distribution of total phenocryst abundances. (b) Triangular diagrams showing the proportions of quanz (Qtz), sanidine (San), and plagioclase (Plag) phenocrysts. (c) Histograms showing the distribution of Or + Cn in sanidine phenocrysts for the rhyolitic ponion of the Tiva Canyon Member of the Paintbrush Tuff at Yucca Mountain, Nevada. There are no data for plagioclase or biotite compositigns. (d) Histograms showing the distribution of Or in sanidine, An in plagioclase, and Mg in biotite phenocrysts for outcrop samples of the quartz latitic ponion of the Tiva Canyon Member of the Paintbrush Tuff at Yucca Mountain, Nevada. Cores, midzones, and rims are undivided in the histogram for plagioclase. There are no data for drill hole samples. 23
l
- 12. Surnmary diagrams showing typical me *.al and mineral chemical compositions for rock units at Yucca Mountain, Nevada. (a) Proportions of felsic phenocrysts (b) phenocryst abundances, (c) Or + Cn in sanidine, (d) An in plagioclase and (c) Mg in biotite.
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-g 6 - UNIT A No. of Samples: Otz
$* I -
. UCW G-1 17 Units A B, and C
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= USW G-3 o ue25-pal Tota:
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0 Ue25-p#1 g 0 to 20 30 1 - W y 3 UNIT B No. of Samples: To 2 - E 1
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, No. of Samples: go
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2 o Ue25-pal 3 I. g 4 Total 27 UNIT E ~* 1 0 _l 7 . . . . . . -- NIT C z o * * * *> Plag e- . 0 10 San 20 30 Phenocrysts as % Total Rock P
UNIT A 50 - 20 - No. of Samplos: No. of Samples: C-a - o uSW G-1 8 8 USW G-1 3 _ E . . a _
*
- 10
- j 25 - - - - -
^
4 - _ - ~ z - - - O . 50 r_ 60 70 0 .
. c. , smu.An50 s 0 . .
10 20 30 40 50 30 40 50 60 70 s - UNIT B 15
- No. of Samples: No. of Samplos:
- USW G-1 2 6
- USW G-1 2_
'm'
- USW G-2 1 -
$C 10 Total 3 g *
* . No. of Samples:
6 5
- USW G-1 1 z -- -
2 - 1 - 0 , IM_H] _ 0 , IT U 2. , ,_ 0 , , , 50 60 70 10 20 30 40 50 30 40 50 60 70 UNIT C 30 - - No. of Samples: No. of Samples: No. of Samplos: 6- _
- USW G-1 5
- USW G-1 6 a **
- USW G-1 2 a 20 -
20 A USW G-? 2 ~ A USW G-2 2 , g -- Total 8 -
- Total 4 E . . -
3 - {0 10 10 - al a 6 _ 5 ' 0 , ,
.. _ _ _ 0 , ,
1
- =
0 , , , 50 60 70 10 20 30 40 50 30 40 50 60 70 Or + Cn in Sanidino An in Plagioclaso (M9/(M9 + Fo)) x 100 in Biotito (n,
',3c4b (a) (b)
Lithic Ridge Otz
.
- USW G-1
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.ll[
o J-13 a 3
- Outcrop 8 E 4 Samples 2 2 2 3 3 1 i o
' Z O ,~ '
o 0 30 - fo. 30 15 i l f No. of Samples: j
. 2-
- USW G.1 23
- a USW G-2 3 I *E 10 3
* = USW G-3 14 g - -
o o Ue25-p#1 2 3 e
'- ~
o J-13 g O S Total 55 25 - - . o 5 * * . _ . o z se . . . I O .J.r.} ,, g, O to 20 5 *
- Phenocrysts as % Total Rock Pla goo o. 4./" +{3 =
San i t ~_L m w - r-- r
(s a 10 -
%. 4- - . _x g g 1 Sample 1 Sample t; < 5 1 Sample 3 3 2 -
2 O o - - - j _ 0 *
.I 1 0 o 1
30 40 50 00 70 10 20 3'O 40 5'O 4'O 5'O Eio 7'O o . Nd. of Samples: '
; No. of Samples: No. of Samples:
- USW G-1 12 100 -
40 = USW G-1 12 = USW G-1 8
- IJSW G-2 1 J-13 g a USW G-2 2
- USW G-2 2
_.1,_ Taal ; o J.13 _1. 0 Ue25-p#1 2
. 14 Total 15 o J-13 I
$ 75 -
., 30 - -
15 I88I 1 _x a r_. E i E 4 e - o O T> 50 20 - 6 f-10 Z q -. o 3 g o - 0 - ast a 1, - n . o 25 - 2 * ' 10 A [-- n _ 5 -
* * * * ^ ~
i - l . '_ $ g >An50
.. . .. . . I P O ,
dg .i. f.le ;b-_ 0 E -
'! .; mm. =*
i* 30 O , 40 50 60 70 10 20 30 40 50 40 50 60 70 Or + Cn in Sanidine An in Plagioclase (Mg/(Mg + Fe)) x 100 in Biotite h
OG +b (a) (b) Otz Tram
?
- USW G-1
. #
- USW G-2 y " USW G-3 i 3 _
sy 2 - 3 Saes a USW G-4 o .
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- E 1'O 20 s
- Outcrop i.
15 I No of Samples:
; , ; . .USW G-1 24 . =
g 4.USW G-2 1
. 3 -n --
= USW G-3 18 o
4 to #* o USW G-4 { } 1 I a . o. o 0 Ue25-pel 3 f **"."). 5 0 E - - - o J-13
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O 10 20 30
'henocrysts as % Total Rock Plag - - - -
San C
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, 3 3 Samples -
3 Samples a l 3 Samples
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50 60 70 10 20 30 40 50 30 40 50 60 70 n 150 60 ~30 - No. of Samples e No. of Samples: No. of Samples:
- USW G-1 14 o I . USW G-1 14
- USW G-1 13
- USW G-2 3
- l
- USW G-2 3
~
o 0 Ue25-p#1 2 l a Ue25-b#1h 4 0 a Ue25-b#1h 5 o J-13 O Ue25-p# 1 2 o , _2 o J-13 _2_ l ._ Total 17 o J-13 _2_ - Total 25 100 40 - 20 - Y j - . 5 S. - I w -
- 5 N i b 3 .
o o 50 4 20 10 -
.10 > An50 *
- 0 i,s ,
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o . . o s ; 9 0 . ,[.,h _ _ _ __ 0 _jE kb -eB *
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- _ HQ .
50 *60 70 10 20 30 40 50 30 40 50 60 70 Or + Cn in Sanidine An in Placioclase (M91(M9 + Fe)) x 100 in Biotite a
Sa4b (b) Bult.~rog Otr (a) !
- USW G-1
- USW G-2 o USW G-4 E o J-13 i e Outcrop 4'
, f 11 Samples
- a8 -
na ' 5i l[l_ d z O y 0 1'O 20 3'O o g No. of Samples: g 10 -
- USW G-1 24
,, To a USW G-2 5 j 4 L* = USW GU-3 7 I a -
3 o USW G-4 1 ", E B . , 333 A Ue25-a#1 3 , 3 _ O 2 , , o J-13 _4 ,A , Total 44
* *= 4 ,o B - -
6 sii o e , e'
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'a e Phenocrysts as % Total Rock , o Plag _ San
[
20-L bC 60 - 30- _
. 7 Samples 7 Samples 7 Samples e -
E 40 - 20 - 10 -
. m a c 20 - 10 -
d *d TJ- - O'50
], a i JL Og I , 0_r-L>l7 , ,
0 50 10 50 60 70 to 20 30 40 50 , 30 4'O 6'O 4 , A s a 0 - 0 o 100 - 100 - 1 20 - o No. of Samples: a No. of Samples: No. of Samples:
~
g
- USW G-1 13
- USW G-1 13 - -
' USW G-1 8
- R A USW G-2 1
- USW G-2 3 A USW G 2 3
.yj a Ue25-a#1 A Ue25-b#1h 3 1 a Ue25-a#1 a Ue25-b#1h 3 2 a a a Ue25-b# 1h 1 o J-13
-< #g
_1 [ 0 Ue25-p#1 0 Uc25-p#1 Total 13 53 , 1 ' J-13 1 E J-13 _.1 50 _1 10 z6 50 o Total 20 Total 23 a g Err i 5 _
!. f .a.
o - - 0 , [ , O hs 10 *
* - efE 30 1 [ .uRIsl_*
40 I 50
'O 30 f5 40 il ,
50 60 10 50 60 70 20
- Or + Cn in Sanidine An in Plagioclase (Mg/(Mg + Fej) x 100 in Biotito
-D
6aso (b) Otz Prow Pass ,. . (a) l
- USW G-1
' USW G-2 o
= USW G-3 USW G-4 g 2- o J-13 eo 4 Samplos "
s i . _
- Outcrop 0 o l g O to 2'o o
.L 15 -
NO of Samples:
',~ g l
! E
- USW G-1
- y. _
G-2 to l 2 U 10 .
* = USW GU-3 6 I
B < o USW G4 2 I 'Ei ._ a Ue25-a#1 g
- E ~
l a5 2E o J.13 5 -
- a .- ^ Total e Ii ,
a -
, ?_.4 2 7 l
I O I43 , gh , ,q 10 20 3'o * "* I o
- O AD, 4 Phenocrysts as % Total Hock a
e* g Plag , San 90 .
~
h b& 20 - _ 10 - a 2 Sampics E - 2 Samples 2 Samples o . t; b - 5 g 3-O <c 10 - 5 - o 2 - - _ An50
, o -
q 1 - - - Z 0 m O I,_ l , O l~] RI, 1 ,1 0 , , j, 40 50 60 70 10 20 30 40 50 30 40 50 60 70 60 o 60 - No. of Samples: A No. of Samples:
^
- USW G-1 5 -
- USW G-1 5
- USW G-2 5 a USW G-2 4 a Ue25-a#1 7 ^
, a Ue25-a#1 5 o Ue25-p#1 2 --
o J-13 1 U 40 o J-13 40 _U I5 1 Total y
.2- Total -- 20
= E 5 I b No. of Samples:
^ *
- USW G-1 3
$ o J-13 1
# Total 4 20 a 20 -
5-0 a
- _ a "
[ o 3
-o on _ _ _ _
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"
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; 6 o No. of Samples: as e 8 h *
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- l l
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- Ue25-p#1
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=
= USW GU 3 27 o USW G-4 22 No. of Samples:
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/
- USW G-2 4 E i
- Total lij
= USW GU 3 8 [
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.__. San e \ % A.1212 4 San
8c 150 -
' ~
^
No. of Samples: _
~
No. of Samples: -
^
- USW G-1 5
- USW G-1 5
- USW G-2 7 a
- USW G-2 7 40 - o USW G-4 12 (_ _. 100 -
o USW G-4 14 g E a Ue25-a#1 13 _ o - A Uo25-a#1
, 0 Ue25-p#1 _1 2 -
1 Total 43
- Total 38 A j o g 30 - -
3 < 75 - - No. of Samples: f 4 0~ E kt
- USW G 1 4
* * -4 6 -
!
- USW G 2 4 o 20 -
he _^
~
._ 50 -
a 10 R Total 5 z g ai _, o g g f. g
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25 - n - II '
** > ^ WE - -
*i
~ ' '
0 Mo]_R{ IHh b gm 0 X - -- H 4[b, o 0 i 11415161 , M
, [M ,
30 40 50 60 70 10 20 30 40 50 ' 30 40 50 60 70 Or+Cn in Sanidino An in Plagioclase (MgI(Mg + Fe)) x 100
; in Biotite i
K ...
bb d 30 - 30 - 6 Samplos 6 Samples ' m 6 Samples 10 20 Q20
. n T.
3 o5 _y 10 - S - 10 - 6 -
> An50 z - - -
L 0 ,, r, O ' l O_ _ ' 0 l 20 $0 40 5'O G'O lO 2'O $0 4'O 50 60 7'O 80 1 h 50 - 40 - 40 5 20 No. of Samples: "
, No. of Samples: No. of Samples:
3 a USW G-2 2 ?
- USW G-1 3 o a USW G-2 2 o USW G-4 4 * * <
o USW G-4 4 -- a U 225-a#1 1 _E , 30 - a Ue25-a#1 3 [_o 30 15
- a. ' _
a Ue25-a#1 3 g o J-13 y* o J-13 _1 _
^
g o o _ H o J-13 _2 Total _1 4
=b Total 10 .;- - e a Total 12 ^ ^
c y o
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- in Biotite J[
9
~
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9od (a) (b) Otz Pah Canyon Member i 4 USW G-2 a Ue25-a#1 E o Outcrop ac - h ~g 3- -
$ $2 -
- o 'd 4 Samples 3 _ _
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). ^
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< a i No. of Samples: No. of Samples:
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^ A Ue25-a#1 1 ^ ^ ^
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IO-i
~ All data for USW G-2 8 All data for USW G-2 3 Samples -
, 3 Samples ,
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- 10. 20 30 Y
h 8-- 0
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Q
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= Total 2-O 10 '
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Tiva Canyon Member I'N
= USW G-3 o Ue25-p#1
- Outcrop 1
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4 ( . i i i - l i STRATEGY OPTIONS
- o REDRILL S3_ECTED "OLD" BOREHOLES
- o i
o UTILIZE DATA / CORE FROM "NEW" BOREHOLES AS REPLACEME QUALIFY SOff SUBSET OF EXISTNG CORE / DATA RESOURGS 1 TIE /SCFEDULE NRC ACCEPTANCE I i l - l . 4 s I 1
A SUNNARY SUNNARY OF TW CURRENT POSITIONS OF TW PARTICIPATING ORGANZATIONS ON TW OENTFICATION OF EXISTING I44WSI PROJECT BOREHOLE S/AFLES THAT MAY BE USED TO SUPPORT UCENSING DOCUNENTS: RESPONSES TO A Lt-iIt-R (DTD. 5/2/88) FROM C. GERTZ WNPO/PM TO TW TPO'S o CORE FROM CONTNUOUSLY CORED HOLES PEETRATING , TOPOPAH SPRNG APO CAUCO HLLS TUFFACEOUS BEDS WILL NEED TO BE CONSIDERED FOR QUAllFICATION GS IDENTFES SIX BOREHOLES; USW G-1, 2. U3, 3, 4, UE25A-1 LAM _ DENTFIES ME BOREHOLES; ABOVE PLUS UE25-b1H, pi, Af0 J-13 ~ 0 _ _ _ ___m__..m _
I I I ! l I l I l l l l l l l l l l l l l l 1 I y_ e'4 4 UE 25 all Q D __ _L - ----- ^ q- - I h I h gl, J G I-
- Af!
USW GU-3 g
- 1 m y l -/
/
q b \
\l n ' ) '
i il I i l l I I l 1 l l l l l l _ s l 1 l l l l 1 I asse.eee si e.eee
- n-way
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- ATE,"u".^L colluvium T 5,4*
l l l n.}} M
; @ gNE#LIOCENE -tg A
Mo'en% ! N 1 N SIDE: 'i CONCEALED , O TSON
; .. 1 EW*^m sua I l
[ , nu m ll 7 i :: EA W oute O -
- l!
h""" "'" ( , 1 CRATER FLAT I i M F T
. .! ,s g nevaaa
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r s - 4 er a a.a et G
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_::: ' . ~ J' ' ~~~ ~"~'
~~
c. 4 ISSUES ISSUES TO BE RESOLVED PRIOR TO TW RECOGMTION OF A SUBSET OF EXISTNG CORE SAWLES FOR QUALIFICATION o FNAUZATION OF TW DRLLNG PROGRAM. AT YUCCA MOUNTAN NUNBER, TYPE Af0 LOCATION OF EW BOREHOLES DRLLING SCHDlLE o SCHDUUNG NPACT OF TW RtitIIIKJN OF EXPERiNENTS WATER / CORE GEOPHYSICAUN-SITU NSTRUNENTATION O
=_.= =-- -
.= .. .. - . . _ .
i . i PROCEDURES & FACIUTIES , PROCEDdRES abo FACILITIES REQlJRED FOR A QUAUFICATIO EFFORT o TRANSFER OF CORE / CUTTINGS TO TW SAMPLE MANAGEM'NT FACIUTY MUST BE COMPLETED o o SAMPLE MANAGB&NT FACILITY MUST BE FULLY OPERATlGNAL AP 5.9Q "QUAUFICATION OF DATA OR DATA INTERPRE-TATIONS NOT DEVELOPED UbOER TH NNWSI PROJECT QA PLAN" MUST BE APPROVED i e
~-
,r.
, STATUS OF AP 5.9Q QUAlFICADON_OF EXISING_ DATA OR DATA INTERERETAllON.NOT DEVELOPED UtCER_IEE hNWSI QA PLAN o NTERNAL T& MSS REVIEW CONPLETED l
- CONffNT RESOLUTION N PROGRESS o '
ESTIMATED TPsANSMTTAL FOR WMPO REVIEW
- AUGUST o APPROACH
- NRC GTP ON QUALFICATION OF EXISTNG DATA [6/87)
UTU7m
- INCLUDES COWIRMATORY TESTNG CORROBORATNG DATA .
EQtAVALENT QA PROGRAM PEER REVEW ~
l ;
^
^
~
l i PROPOSED WORKNG GROUP e . i { ! A GROUP COMPOSED OF NEMBERS FROM TFE SAMPLE OVE ! CONtdiItt, PROJECT REGULATORY COMPUANCE, Af0 ! QUALITY ASSURANCE WOLA_D BE CHARGED WITH DEVELO I . PROTOCOL FOR QUALFYNG EXISTNG CORE /CUTTNG Af0 j RELATED BOREHOLE DATA FOR USE AS PRNARY DATA N ' UCENSNG DOCUMENTS , 9 O h- a__ _ _
l f Attachssnt 3 l l Page 1 of 1 , Use of Existing Core for Licensing l Most of the studies for geochemistry require that we characterize all units across the repository. block and along possible transport pathways to the accessible environment. Single key intervals used in these studies cannot be identified. We need all data obtained to develop a three dimensional model of Yucca Mountain. The studied do fall into two groups, however and these can be discussed separately. The least restrictive (in terms of core identification ) studies that we do are assentially generic. It is not necessary to independently identify the core or interval from which the sample came. The core is characterized using XRD, XRF and petrographic microcsope description of thin sections. From this information it can be determined what unit, and often what lithologic interval within the statigraphic unit is present. The results are tied to lithology, mineralogy and chemistry. To demonstrate the appropriateness of the results to Yucca Mountain it need only be demonstrated that the lithology, mineralogy and chmistry of the samples used in these studies match the intervals of interest at Yucca Mountain. Samples can be taken from future drill core or the exploratory shaft as appropriate to demonstrate this relationship. Studies that fall into this category are sorption studies and glass dehydration studies. For some of the sorption studies natural state samples have been used, and if those are accepted as QA Level-1 they will provide additional tie points to Yueca Mountain, but this should not be necessaary for acceptance of the data for licensing. The second category is the one that most Mineralogy-petrology studies fall under. Waxed core has not been used in these investigations. Key samples I cannot be identif *6d as it is necessary to characterize sorptive barriers along hydrologically transmissive zones across Yucca Mountain. Identification of the borehole from which the samples came is necessary. l Vertical control to within +-50 f eet is desired. If waxed core is accepted as QA Level 1, selected pieces could be analyzed to coroborate existing data for some activities, but probably would not be of much use for fracture mineralogy, many samples are examined and interpretations are based on a l l suite of samples rather than single occurrences. Misplacement of one or two l samples would have no effect on results. Interpretations are tied to j lithology and stratigraphy (independently determined) as well as depth, 1 Data collected is internally consistent within stratigraphic intervals and betaeen drill holes. Discussion of internal consistancy is contained in the report by Broxton et al. (milestone T095, copy enclosed). l
. p e-NEED FOR THE QUALIFICATION OF EXISTING DRILLHOLE SAMPLES POSITIONS OF THE PARTICIPATING ORGANIZATIONS ON THE IDENTIFICATION OF EXISTING NNWSI PROJECT DRILLHOLE SAMPLES THAT MAY BE USED TO SUPPORT LICENSING DOCUMENTS:
RESPONSES TO A LETTER (DTD. 5/2/88) FROM C. GERTZ-WMP0/PM TO THE TPOS U.S.GE0 LOGICAL SURVEY: Initial Response
' Virtually all of the existic9 core and bit cuttings were used in the preparation of lithologic logs which were published or will be published in drillhole basic data reports. These data reports, in turn, have been and will continue to be used and referenced in our interpretative reports, position papers, and NNWSI Project licensing documents. We cannot determine that any specific sample will or will not play a part in the licensing process. In fact,every existing sample is susceptible for selection as the basis for some scientific interpretation, analysis or conclusion that can be used in support of, or against, licensing. Therefore unless you intend to exclude all USGS drillhole basic data reports from the licensing process, all drillhole samples, including core, cuttings and water from either the saturated zone or extracted from rocks of the unsaturated zone, should be considered as~ candidates for qualification".
Revised Response
~The two major stratigraphic intevals that we have selected are the Topopah Spring Member of the Paintbrush Tuff and the tuffaceous beds of Calico Hills.
The intervals include the host rock and the potential barrier between the repository and the water table, respectively. Characterization of samples from these intervals are considered a high priority. Other considerations are intervals that include contacts between subjacent stratigraphic units, which help establish the primary geometric configuaration of the respository area. We have included only continuously cored hoice in this selection process. Although all holes where geophysical logs and bit-cut'eing samples have been collected represent an integral subset of data for establishing the geologic framework of Yucca Mountain, continuously cored holes have provided the fundamental reference data set, from which reliable lithologic and geophysical correlations are made. Coreholes that penetrate the above mentioned stratigraphic units within or near the area enclosed by the perimeter drif t are presently considered more important for labar use in licensing interactions end are given a higher priority. t I . . .
4
/ ,~
2 LOS ALAMOS NATIONAL LABORATORY:
"Key intervals from specific cores can be identified for the alteration history and tracer evaluation studies. However, our work on the mineralogy of transport pathwayc and fracture mineralogy requires characterization of all units across the repository block and along potential ground water flowpaths to the accessible environment. To do this, a complete three-dimensional picture of the n; seral distributions at Yucca Mountain must be constructed. We feel that use of limit.ed subsets of existing data will not be dequate to document the many changh in mineralogy that occur vertically and laterally at Yucca Mountain."
Attachment 1 - Provides a list of boreholes, identification of analysis completed, accuracy, and sensitivity of sample depth and location, and estimates cost and time to duplicate tests. Attachment 3 - Oraf t Report by Broxton, Byers, and Werren proposing and compiling information for a possible peer review of data from nine boreholes; six are the same as proposed by the USGS. SANDIA NATIONAL LABORATORIES:
"Existing data and data from ongoing activities with ' unqualified core' may, as necessary, be used as supporting or corroborating information in the licensing process. Our plans for obtaining primary data require samples from new coreholes at Yucca Mountain and most of our requirements are for samples from locations that have not been previously cored. Therefore, we cannot identify a
- specific subset of existing core that, if qualified, would significantly change our requirements as expressed in the SCP. If the planned drilling were greatly reduced, the reductior, might force us to attempt to use existing core for gathering future primary data. The nature of such reduction would dictate our specific qualifying requirements".
LAWRENCE LIVERMORE NATIONAL LABORATORY:
"Although we have received core or cuttings samples from various depth intervals in eight drillholes on or near Yucca Mountain and have used some of the material in experiments, none of these samples need be qualified if repository horizon samples become available in a timely manner."
SUMMARY
OF POSITIONS: The positions range from: '
- 1. All of the existing core / cuttings should be considered for qualification because much of the data derived from drillhole samples (e.g. subsurface stratigraphy) has already been released in reports which will be referenced in licensing documents. This position was subsequently modified to include only 9
, 1 /
ib 3 SUYMARY'Of POSIT 0NS: (Cont'd) the major. subset or data f rom continuously cored holes penetrating the Topopah Spring Member of the Paintbrush Tuff and the Calico Hills tuffaceous beds. Coreholes within o~r near the perimeter drift are of mcst importance.
- 2. Perhaps none of-it will need to be qualified. The latter position intends that new core will meet all of the Project requirements toward resolving licensing issues, but with the caveat that time constraints (e.g. the need to meet (e.g. Project deadlines) or restrictions on drilling in the repository bic:k
- r. umber some drillhole of holes and/or depth sf holes) might create a need for qualifying samples. '
i ISSUES TO BE RESOLVED PRIOR TO THE RECOGNITION OF A SUBSEr 0F EXISTING CO SAkPLES FOR QUALIFICATION
- 1. FINALIZATION OF THE DRILLING PROGRAM AT YUCCA MOUNTAIN: What restrictions on number of holes or their depth will be placed on the Project? For example, no drilling below the water table may mean that all core from the Crater Flat Tuff will have to be qualified. Does the present Drilling Program reflect the possiblity that existing drillholes might not be part of the primary data set?
- 2. SCHEDULING IMPACT: What will be the impact on the present schedule if the existing data derived from drillhole samples can not be used as primary data and some tests and experiments must be duplicated? These experimeats and the related coro/ cuttings samples would have to be identified. It has been suggested that delays up to five years (e.g. sorption experiments) may result.
PRGCEDURES AND FACILITIES REQUIRED FOR A QUALIFICATION EFFORT
- 1. STATUS OF THE CORE TRANSFER: For any technical study of the actual drillhole material preparatory to a qualification effort the drillhole samples will have to be in storage at the Sample Management Facility (SMF) . The transfer is-in progress and core / cuttings from 16 holes has been moved to the SMF.
The projected completion of this activity is late 1988 to early 1989.
- 2. STATUS OF THE SAMPLE MANAGEMENT FACILITY: This facility must be operational prior to any work on the existing material (e.g. relogging of selected intervals or the preparation of gamma logs from core). SMF technical procedures and administrative procedures are in formal review. Computer software is being developed, however, the establishment of a 56 kilobit communications link for the full operation of the SM" computer system-and the software has not been resolved. The software will have to be reviewed and approved.
3. STATUS OF AP 5.9Q QUALIFICATION OF DATA OR DATA INTERPRETATIONS (EXIS DATA) NOT DEVELOPED UNDER THE NNWSI PROJECT QA The PLAN: AP is under formal review. It is important to the qualification of existing core because it v o
4 establishes a cutof f date for NNWSI Project produced existing data as being data generated before the QA Level assignment to the activity (AP 5.9Q replaces NNWSI Project 50P 03 03 which defines existing data as data generated prior to the
- August 1980 version of the NNWSI Project QA Plan and therefore eliminates much of the core from the existing data' category). Also AP 5.9Q utilizes the four methodologies for qualification described in the NRC Generic Technical Position Paper on the "Qualification of Existing Dats". These four methodologies and examples of their application to the drillhole data are listed below.
Corroborative Data: A comparison of~the petrology of semples collected from stratigraphic sections at the surface and from the ESF sampi' sites with existing drillhole samples is an example. Confirmatory Testing: The application of geophysical logs from the existing drillholes to the recognition of stratigraphic units defined initially on the drillhole lithologic logs is an example. QA Program: An activity controlled by procedures similar to a 10 CFR 50 Appendix 8 Program might be the documented acceptance procedures and detailed technical procedures used in the geophysical logging of NNWSI Project drillholes. These may be sufficient to qualify the drillhole stratigraphy. Peer Review: A panel of experts external to the project who would review a protocol put together by the NNWSI Project. This protocol would be a plan covering the technical methods and document analyses required for the qualification of the existing drillhole data. PROPOSED WORKING GROUP The purpose of this group would be to assemble and evaluate documents and technic:l methodologies in support of the qualification of existing data utilizing the guidelines in AP 5.9Q. This group would davelop a protocol for qualifying existing core / cuttings and related drillhole data to be used as primary data in licensing documents. It's members would be drawn from the Sample Overview Committee, Project Regulatory Compliance (Licensing) and Quality Assurance.
6 l I CHARTER FOR THE SAMPLE OVERVIEW COMMITTEE RATIONALE , . Geologic samples provde i b as the ifs or deve hfho t it l iop ng muc e s ehc aract erza i ti a a relative on dt l to the suitability of Yucca Mountain as a geologic repository for high-level radioactive waste. The Sample Overview Committee (SOC) was formed to ensure that Nevada Nuclear Waste Storage investigations (NNWSI) Project sample care and disbursements meet the needs of the NNWSI l Project and satisfy the requirements specified in the NWPA,10 CFR 60, NNWS1 Site Characterization Plan Chapter 8, Study Plans, and the Waste Management Project Office (WMPO) l Quality Assurance Program Plan (WMPO 881, Rev. 0). PURPOSE OF SOC i The purposes of the SOC are to: o Serve in an advisory capacity to WMPO regarding the distribution and preservation of samples for the NNWSI Project. o Evaluate requests for samples with respect to U.S. Nuclear Regulatory Commission (NRC) regulatory, U.S. Department of Energy, and NNWSI Project requirements, o Evaluate request for samples from outside the project (e.g., the state and the NRC) with respect to impacts upon future NNWSI Project needs. o Evaluate that adequate procedures are developed for distribution and preservation of samples and that procedures meet Quality Assurance LevelI requirements for use in NRC licensing. o Assure representative samples will be archived from coreholes, drill cuttings, exploratory shaft, drift mining, trench activities, and other field or laboratory activities deemed appropriate. MEMBERSHIP OF SOC Each of the major NNWSI Project participants involved in the care, disbursement, or use of geologic samples for site investigations in support of site characterization will be represented on the SOC, the WMPO representative serving as the SOC chairman. This includes representatives of the Sample Management Facility (SMF) and Quality Assurance.
'the Technical Project Officer for each of the member organizations shall select a representative for the SOC. Member organizations may designate an attemate to attend meetings and/or act in a representative's place on a temporary basis.
MEETINGS Meetings or teleconferences will be held on Tuesday of the first full week of cach rnonth unless the SOC agrees to an afternate date. The SOC Chairman will notify members of attemate meeting dates and locations. Teleconferences may be arranged at other times when conditions warrant such action or at the request of the member organizations.
e ACTION The SOC wi!! provide a written recommendation to the WMPO Project Manager regarding 9ach sample request reviewed by the committee. WMPO, LLNL, LANL, SNL, SAIC and the USGS will have one vote each: The SMF representative and the OA representative will serve in an advisory capacity to the SOC. The WMPO will approve or disapprove the SOC recommendation. The SMF Manager will disburse samples upon receipt of an approval memorandum from the WMPO Project Manager. The recommended actions will be: o Approved o Disapproved o Tabled The SOC will identify the reason (s) why requests are tabled or disapprosed. Requests tnat have been disapproved may be resubmitted at a later date. Minority opinions are to be included in the recommendation to WMPO. DUTIES OF SOC MEMBERS SOC Members will represent their respective organizational sample needs and request. Attematively, the Pl may present his/her request at the discretion of the SOC representative. SCC members will evaluate sample requests, resolve conflicting sample requests, and make recommendations for sample disbursements to the WMPO Project Manager. The SOC Chairman will prescot the sample requests from NNWSI Project participants not represented on the SOC and &m organizations outside the NNWSI Project. Other duties of the SOC Chairman include periodk: ccmmunications with the SMF Manager, coordination of sample requests from outside organizations. calling of special meetings of the SOC, serving as liaison between the WMPO and the SOC, usuring adequate procedures are developed and implemented, and presenting SOC n.mmmendations to the WMPO Project Manager for approval. The SMF Manager will disburse samples as directed by the WMPO Project Mr..iager. The SMF Manager will provide the SOC with an updated sample status and availabilit/ report and aid the SOC in assessing the NNWSI Project sample needs. DELEGATION OF AUTHORITY In accordance with the WMPO-OAPP, WMPO/88-1, Rev. O, the Chief of the Regulatory and Site l Evaluation Branch is responsible for irrplementing this charter. I l l l l l l l l _ n
T INFORMAL INPUT NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECT ADMINISTRATIVE PROCEDURE AP SOC-1 APPROVAL PROCEDURE Oc REOUEST FOR NEVADA NUCLEAR WASTE STORAGE INVESTIGATIONS PROJECT GEOLOGIC SAMPLES 1.0 PURPOSE AND SCOPE This procedure desenbes the Waste Management Project Office requirements and responsibiinies for disbursoment of Nevada Nuclear Waste Storage Investigations (NNWSI) Project geologic samples. 2.0 APPLICABILITY This procedure applies to all geologic sample collected in support of site characterization. Geologic samples include those obtained from boreholes, the Exploratory Shaft Facility (ESF), and surface outcrops and trenches. 3.0 DEFINITIONS 3.1 NNWSI PROJECT The NNWSI Project consists of a variety of geotechnical studies conducted as part of the U.S. C?partment of energy's (DOE) Otfice of Civilian Radioactive Waste Management (OCRWM) prograrn To satisfy the requirements specified in NWPA,10CFR 60, NNWS! Site Characterization Plan, Chapter 8, Study Plans, NNWSI Project Quality Assurance Procedure, and the Waste Management Project Office Ouality Assurance Program Plan gWMPO-88-1).
. 3.2 WASTE MANAGEMENT PROJECT OFFICE The Waste Management Project Office (WMPO) is assigned by DOE, Nevada Operations Office (DOE /NV), to administer and coordinate the mcnarprient and technical direction of the g activities of NNWSI Project Participating Organizations and tne Nevada Test Site (NTS) Support Contractors.
3.3 SAMPLE OVERVIEW COMMITTEE The Sample Overview Committee (SOC) is the organization responsible for assuring that all the NNWS! Project Participating Organizations and outside organizations are provided with geologic samples for site investigations testing and examinations and that representative samples are retained for archiving. Each of the major NNWSI Project Participants involved in use of geologic samples for site investigations in support of site characterization serve in an advisory capacity. The WMPO representative serves as the SOC Chairman. Represerriatives of the TechnicalIntegration and Support Division, the Sample Management Facility, and Quality Assurance Department of Science Application Intemational Corporation serve as advisory members of the SOC. The SOC processes and approves sample requests from various NNWSI Project Participating Organizations and outside organizations, based on future NNWSI Project needs. SOC assures that adequato quality related administrative procedures are developed for distribution and preservation of samples, and implementation of these procedures meets the requirements for NRC licensing.
V I l l 3.4 NNWSI PROJECT PARTICIPATING ORGANIZATIONS l l NNWSI Project Participating Organizations consist of various National Laboratories, i.e., l Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), and Sandia National Laboratories (SNL), the U.S. Geological Survey (USGS) an any other NNWSI Project contractor conducting hydrologic or geclogic site investigations. 3.5 TECHNICAL AND MANAGEMENT SUPPORT SERVICES CONTRACTOR The Technical and Management Support Services (T& MSS) contractor provides technical operational management support to WMPO. The T& MSS contractor is responsible for administrative management of the Sample Management Facility. 3.6 NNWS! PROJECT SAMPLE MANAGEMENT FACILITY The NNWSI Project Sample Management Facility (SMF) consists of two storage & handling buildings located in Area 25 of the NTS. Personnel assigned to the SMF are respcnsible for transferring, receiving, handling, processing, archiving, and disbursement of geologic samples in suoport of a DOE license application to the U.S. Nuclear Commission (NRC) for a mined geologic re msitory. SMF personnel support the SOC by tracking and disbursing samples and document s, and generating sample status reports. 3.7 SAMPLE Examples covered by this procedure include core, cuttings, fluids, and other geologic samples collected at the NNWSI Project field sites as part of approved Project study SCP study plans and associated activities. 3.8 EXISTING SAMPLES Existing samples are samples that reside at the SMF or are in custody of a participating organization at the time of the request for allocation. 3.9 PLANNED SAMPLES Planned samples are samples which are a part of a SCP study plan or activity and have not been collected at the time of the request for allocation. Details for collecting these samples may not be available at the time of the request for allocation. 4.0 RESPONSIBILITIES 4.1 WMPO PROJECT MANAGER The WMPO Project Manager is responsible for designating NNWSI Project Participating Organizations to be represent ,d on the SOC and reviewing and acting on sample request recommendations submitted by the SOC. 4.2 REGULATORY AND SrTE EVALUATION BRANCH CHIEF in accordance with the WMPO-OAPP, WMPO/08-1 Rev.1, the R&SEB Branch Chief is responsible for technical management of site characterization activities including the Sample Management Facility.
l V 4.3 SOC CHAIRMAN The SOC Chairman is responsible for calling and chairing meetings o' the SOC, preser' ting sample requects from non-member organizations to the SOC, and presenting the recommendations of the SOC to the WMPO Project Manager for consideration. SMF Manager - Disburses samples as directed by the WMPO Project Manager, provides the SOC with periodic updated sample status reports, and assists the SOC in assessing NNWSI 4.4 MEMBERS OF THE SOC Memoers of the SOC are responsible for representing their Participating Organizational sample needs and requests, integrating NNWSI Project cunent and futu e sample needs, resolving conflicting sample requests, and submitting sample requests to the WMPO Project 4.5 TECHNICAL PROJECT OFFICERS The Technical Project Officers (TPO) for each of the member organizations is responsible for selecting a representative to the SOC. 4.6 T& MSS PROJECT MANAGER The T& MSS Project Manager is responsible for selecting the Technical integration and Support Division, Sample Management Facility, and Quality Assurance Department 5.0 PROCEDURES
5.1 INTRODUCTION
The SOC has been established to evaluate requests for samples with respect to current and future NNWSI Project sample plans and needs, and to assure preservation of representative samples deemed appropriate by the WMPO Projec' Manager. This Administrative Procedure establishes the procedures for sample requests, control, and disposition. 5.2 SAMPLE REQUESTS FOR EXISTING SAMPLES For existing samples, the steps outlined below will be followed for each samole reauest
- a. Each Principal Investigator (PI) identifies sample needs and prepares a sample request.
- b. The PI's SOC representative sends copies of the request to the SOC Chairman and members
- c. SMF personnel measure the intervals that have been requested.
- d. The SOC Chairmar and the SMF Manager prepare an allocation imoact evaluation to be distributed to the SOC members.
- e. SOC representativen of Pls presents the sample request to the SOC for action.
- f. The SOC evaluates 11e sample request, integrates current and future sample needs, and submits a recomrrendation to the WMPO Project Manager,
- g. The WMPO Projec. Manager will act on the SM recommendation and samples are disbursed as directed.
4
5.3 SAMPLE REQUESTS FOR PLANNED SAMPLES For planned samples, the steps outlined below are followed for each sample request:
- a. Each PI develops a preliminary drilling, testing and sampling plan and transmits it to the WMPO.
- b. The WMPO reviews and distributes copies of the sampling plan to each SOC member.
- c. Other Pls identify additional samples needed and prepare sample requests.
- d. The PI's SOC representative sends copies of the requests to the SOC Chairman and members,
- e. The SOC Chairman prepares an integrated sampling plan to be distributed to the SOC members,
- f. The SOC reviews the integrated sampling plan and submits a recommendation to the WMPO Project Manager,
- g. The WMPO Project Manager acts on the SOC recommendations and directs samples to be collected as per the approved integrated sampling plan.
l I
INFORMAL INPUT Boreholes inventoried at the USGS Core Library through June 7,1988 PROCESSED FROM 5 /31/88__TO 6/7/8P _ USW VH#2 348 Boxes Core TOTAL AS OF 6/7/88 16 holes 24 Boxes Cuttings 137 PVC 1099 Boxes Core 69 Waxed 7 Miscellaneous PALLETS TRANSFERED TO THE SMF Number 1 through 30 PA11ETS LOADED ON TRANSFER TRUCK Number 31 through 33 HOLES INVENTORIED TO DATE UE 25 UZ-4 UE 25 C-1 UE 25 UZ-5 USW UZ-6 USW UZ-6s USW UZ-7 USW UZ 13 UE 25 UZ-N10 UE 25 UZ-N23 USW UZ-N47 UE25 C2 UE25 C3 USW G4 UE 25 UZ-N86 UE25 At USW VH2 (Not Completed)
REVISION OF PARTICIPANTS QAPPs MAY .;UNE JULY AUGUST 25 5 12 19 26 3 10 12 24 31 7 14 21 TRANSMIT 88-9 TO PARTICIPANTS O PARTICIPANT REVISION OF OAPPs t i IRANSMIT CHECKLIST TO PARTICIPANTS Q IRANSMIT DRAFT OAPP TO WMPO FOR REVIEW ALONG WITH COMPLETED CHECKLIST Q. WMPO REVIEW I I COMMENT RESOLUTION I I NCORPORATION OF COMMENTS BY PARTICIPANTS i I 'HANSMIT REVISED OAPP TO WMPO O ~ INAL REVIEW BY WMPO I I IIANSMIT OAPPs TO OCRWM FOR REVIEW / APPROVAL O , b
s E-r ! ADDITIONAL POTENTIAL IMPACTS
. CURRENT SCHEDULE BASED UN PRESENT VERSION OF THE NNWSI QA PLAN, NNWSI/88-9 (ISSUED 5/19/88) t
. NRC llAS COMPLETED TiiEIR REVIEW OF NNWSI/88-9, REY. 0; COMMENT RESOLUTION MEETING IS SCilEDULED FOR JULY 8, 1988.
e ADDITIONAL CHANCES MAY BE REQUIRED TO NNWSI/88-9, REV. O AS A RESULT OF NRC COMMENTS. e NNWSI PROJECT PARTICIPANTS WILL BE DIRECTED TO INCORPORATE ANY ADDITIONAL CilANGES VIA Tile REVIEW / COMMENT PROCESS TO THEIR QAPPS; FORMAL REVISION TO NNWSI/88-9 WILL BE PROCESSED CONCURRENTLY.
,_ b
REVISION OF PARTICIPANT QUALITY ASSURANCE ADMINISTRATIVE PROCEDURES MAY JUN JUL AUG SEP OCT NOV DEC ! 6/12 TRANSMIT 88-9 MATRIX TO ' + PARTICIPANTS PARTICIPANTS TO COMPLETE i 7 MATRIX 7/18 SUBMIT COMPLETED MATRIX O TO WMPO 7/18 SUBMIT SCHEDULE FOR O PROCEDURE REVISION ' WMPO INTEGRATE SCHEDULE i PARTICIPANT REVISION OF i PROCEDURES WMPO REVIEW OF PARTICIPANT i PROCEDURES COMMENT RESOLUTION COMMENT INCORPORATION BY r- i i PARTICIPANTS TRANSMIT PROCEDURES AND o VERIFIED MATRIX FOR WMPO APPROVAL TRAINING i L
. AUDIT:
A PLANNED AND DOCUMENTED ACTIVITY PERFORMED TO DETERMINE BY INVESTIGATION, EXAMINATION, OR EVALUATION OF OBJECTIVE EVIDENCE THE ADEQUACY OF AND COMPLIANCE WITH ESTABLISHED PROCEDURES CODES AND STANDARDS INSTRUCTIONS AND DRAWINGS
- OTHER APPLICABLE REQUIREMENTS AS WELL AS THE EFFECTIVENESS OF IMPLEMENTATION 1 MW)ASJC PUB 5/1I/tia 11 .
AUDIT PREPARATION A. SCHEDULING B. PLANNING & NOTIFICATION C. TEAM SELECTION j D. CHECKLIST DEVELOPMENT i i ! E. TEAM BRIEFING WMPOASJC. PUB - 5/11/B8 P4
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SUMMARY
CONFERENCE SUBMITTED PREPARED PREPARED CONDUCTED ' TO LEAD AUDITOR 5.5.1 5.7.1/5.9.1 5.8.1 5.8.2 SDRs FINAL SDRs AUDIT AUDIT REPORT FINALIZED -> TRANSMITTED; + + REPORT APPROVED & i PER P-A SUBMITTED FOR PREPARED DISTRIBUTED CONFERENCE TRACKING DISCUSSION WMPOASJC fMlJ $/3 I/Im 33 si l
l] WMPO STAND ARD DEFICIENCY REPORT $^#38 i Dato l 2 Severity Level O1 02 03 Page 1 of s Discoverec During se identfM By 3b Bearen CNei 4 SDR No. y Concurrence Date
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l <t t 1s Cause of the Condition & Corrective Action to Prevent Recurrence l 17 Effectrve Date - x 18 Signature / Data I is OAmt UAriewed QAEAsac Auditor / Data Brancn Manager /Dats r.ea a 3. ORejoct Response f 2o Amended OAccoot QAE/ Land Auditor / Data Branch Manager / Data rm w O Reject O 21 Verifi- OSatisfactory QAE/Leed Auditor / Data Brarch Manager / Data e caton QUnsatisfactory b 22 Remarks N
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d 2s QAEAsad Auditor / Data ' Branct) Manager / Data ' POM/ Data QA CLOSURE I I s ,
l 1 AUDIT SUP9%RY Audit I Reco m n-riteria Program Element 1 2 3 Observationn dations 1 Orcanirstion 2 Ouality Assurance Prooram Scientific Investigation Control 3 and Design Control 4 Procurement Document Control
' 5' instructions, Procedures and Drawino,s 6 Document Contec1 Control of Purchashed Material, Equipment 7 and Services '
identification and Control of Samples 8 and items 9 Control of Processes 10 Inspection and Surveillances 11 Experiment and Equipment Test Control 12 Control of Measuring and Test Equipment 13 Handling, Storage sad Shipping 14 Inspection and Test Status 15 nonconformances 16 Corrective Actions 17 Quality Assurance Records 4 18 Audits
a AUDIT FOLLOW-UP Au o T C'# A. 411984ME AND RECOftDS PROCESSING i B._ SDRt PR6CES9fNG j
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PROCEDURE REVIEW CHECKLIST
- 1) Verify that the procedure title subject is reflected in the subject of the purpose / scope.
- 2) Verify that the purpose / scope is clearly defined.
- 3) Verify that the body of the procedure reflects the subject stated in the pro-cedure title and purpose / scope.
- 4) Review the procedure for general format to satisfy AP-1.1Q.
- 5) Verify that ' S procedure is identified with a unique number, revision num-ber, date of .. sue (effectivity date), pagination, and has been approved by the appropriate levels of management.
- 6) Verify that the procedure instruction has a logical flow and is clear and understandable.
6a) Verify that the procedure can be performed exactly as written (verbatim compi ianco) .
- 7) Verify that all procedures, specification, etc. are noted in the reference section of the procedure.
- 8) Verify that procedure references in the body of the procedure are issued, properly titled, and the subject is relevant to the procedure being reviewed.
- 9) Verify that if this procedure generates a record, ensure that a records section is part of the procedure and denotes that the record is either commercial or QA.
- 10) Verify that the definition section contains only those peculiar to that particular procedure
- 11) Verify that the requirements of NNWSI/88-9 have been addressed.
- 12) Verify that all interf aces addressed in or by the procedure have been addressed completely and resolutions recorded.
- 13) Verify that checklists and attachments have been addressed properly when referenced in the body of the procedure.
- 14) Verify that organizational and individual responsibilities are identified.
- 15) Verify that appropriate quantitative and qualitative acceptance / rejection criteria are clearly specified (i.e. inspections, tests, work performance, quality compliance, etc.)
DRAFT
- 16) Verify that requirements are incorporated for identifying, docuenenting, and resol v ing discrepanc ie:- sne nonec,nic rmorien .
- 17) Verify that requirements and responsibilities are defined for document control and distribution of records and reports.
REMARKS: SICNATURE DATE DRAFT
SCHEDULE FOR MEE'ING REQUIREMENTS RELATED TASKS '
& WORK EFFORTS TO IMPLEMENT A FULLY 6UALIFIED QA PROGRAM FOR OA 1988 1989 QUALIFICATION
_ JUNE JULY AUG SEPT OCT NOV DEC JAN i PROJECT LEVEL PLANS ,,=,Q, m,Q= _ =O QAPP's O =e ElE-- ~ OA PROCEDURES O _i, , ofmygy QUA11FICAllOfJ/CIRiiF8 CATION Of 11RSCt4NEL (I
/ =
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- 5 -
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PROCESS OF IMPLEMENTING FULLY QUALIFIED QA PROGRAM TASK
SUMMARY
OF PROCESS PROJECT LEVEL PLANS PROCESS DEFINED BY T& MSS MAY 13 LETTER APPROVED BY C. GERTZ ON 6/7/88 OUAL/ CERT. OF PROCESS DEFINED IN WMPO QAPP. LETTER OF DIRECTION COMING PERSONNEL FROM WMPO IN A WEEK TRAINING PROCESS TO BE FINALIZED BY TRAINING MGMT PLAN, IMPLEMENTING PROCEDURES, AND LETTER OF DIRECTION FROM WMPO IN A WEEK TECHNICAL /QA DEFINITION AND CATEGORIZATION (NEW, ONGOING) OF ACTIVITIES TO PREREQUISITES BE DEFINED FROM SCP NETWORKS BY T& MSS (M. PENDLETON) LIST AND CATALOG OF OA TECHNICAL PREREO. TO BE PREPARED BY T& MSS WITH INPUT FROM PARTICIPANTS 4 SAMPLE NETWORKS DEVELOPED FOR HQ REVIEW BY 7/30/88 e 2 ARCHETYPE STUDY PLANS PER TPO DIRECTION
; e 2 MORE STUDY PLANS NEED TO BE IDENTIFIED i
i 2 ONGO!NG ACTIVITIES (CHECKLIST FOR INTERNAL REVIEW ONLY) o HISTORIC AND CURRENT SEISMICITY, 8.3.1.17.4.1 s CHARACTERIZATION OF THE QUATERNARY REGIONAL HYDROLOGY, 8.3.1.5.2.1
. AWM BHF/7-5 88
PROCESS OF IMPLEMENTING FULLY QUALIFIED QA PROGRAM (CONTINUED) TASK SI)MMARY OF PROCESS TECHNICAL /QA PRIORITIZATION OF REMAINING NETWORKS TO BE ESTABLISHED FOR { PREREQUISITES THOSE BEYOND THE 4 EXAMPLES l (CONTINUED) ', NETWORKS WILL BE CREATED FOR EACH ACTIVITY SHOWING { PREREQUISITES AND SCHEDULES i (NOTE: RESOURCES FOR THIS EFFORT HAVE YET TO BE IDENTIFIED) READINESS REVIEW WMPO MAY CONDUCT READINESS REVIEW (S) TO DETERMINE WHETHER PROJECT IS PREPARED TO IMPLEMENT PROCEDURES (OPTION) l l l l OAWM flflf/7 5 08 l l __ . _ __
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S L O D R E BEL D A T _ D E U R ND A N _ O N T N D E U D ONW I E O E A P R I E C T PJ . I C T E A R S C M O R C T . - E I T E U U O NM R R T L D C O P R P E S S E P A P N O N O D N D O ES EU R R O AK 2 R C A R F D T P R ED @ PS T S S N A P s S A R UC ED E O M L 9 I A N M E P A LC PR I O 8 CT T / A & N Q C C 1 T O A RO L / - I P D A RL A 1 T Y D T E PA I E N: C M G RH C B W S O8OLI . N C/8T AN I I I D E V D T AC T R E I V E S18 RICHC R) PAE A R A P8 E R N R S /EN E M Y 7FE H C T M~ OS RK T AD S B T P E /8 Y O & R ED F R S N T B(TE D D R1/ P 9 C N G SO T A EN O SN T TW I N DL E L G A N E I C I N T TUIEEL DA ST EE UP T I T I I I TA LTE UN A D RIT F A UT KAR A A P E TR O R R T P S L N S.EN
- Q EO RN OA P I AA T P T iR I -
RG I RT F E I C MS Y C E E D TQSD HACE PS TT RU EL - C I I T GF NF F T U D I V OP PN RU AD PE N N A R D OD T I I P EH ST A US E I O C B RNeee US RC N J T PA SA PS A L E S V AE E L QT
/I L E S LS S S T N G S AI K C U E T K C N N Q R I D
ES O I NW I NE O S JN S N I DE U I I HR W A A OA R A AV CE T RL E R EE ER E A T PP T RR TP N O l . i l! iij
l l l ISSUES STILL BEING ACTIVELY ADDRESSED I e INTEGRATION OF PROJECT AND DOE /HQ EFFORTS, e.g.,
- WHAT WILL BE PROVIDED TO NRC AND WHEN?
- WHAT LEVEL OF DETAll SHOULD BE ON NETWORKS?
HOW WILL DOE /HQ AND PROJECT QA DOCUMENTS BE MADE TO CONFORM TO EACH OTHER? l i o DEFINITION OF RESOURCES REQUIRED TO COMPLETE ALL ACTIONS ON TIME I j e DEFINITION OF PROCESSES AND ALLOWED TIME PERIODS ) FOR DOCUMENT PREPARATION, REVIEW, AND APPROVAL J l e j PRIORITY OF THIS ACTIVITY vs OTHER HIGH PRIORITY ACTIVITIES (SCP, ESF) . l ) t OAWM Oftf/7 5 88 i
QUALIFIED QUALITY ASSURANCE i PROGRAM i P (QQAP) i l e i DOE COMMITTED TO NRC TO HAVE A FULLY QU I QA PROGRAM IN PLACE PRIOR TO START OF SIT CHARACTERIZATION ACTIVITIES 4 l e l TARGET DATE OF JANUARY 1,1989 e DEFINITION EVOLVING
i l l, QUALITY ASSURANCE ITEMS i' i i !1 l e WHAT IS NEEDED TO PUT IN PLACE A "QUALIFIED" i QA PROGRAM 4 l e METHOD &. SCHEDULE FOR REVIEW AND APPROVAL OF PARTICIPANT QAPPs & QA ADMINISTRATIVE PROCEDURES ' l e THE QUALITY ASSURANCE AUDIT PROCESS : I {
P' i BASIS FOR ACHIEVING A l QUALIFIED QA PROGRAM L l e NETWORK NEW & RESTART OF OLD TECHNICAL { I ACTIVITIES i e e IDENTIFY MINIMUM TECHNICAL AND QA PREREQUISITES l INTEGRATE PREREQUISITES INTO NETWORKS - ! e l DEVELOP SCHEDULE FOR DEVELOPING AND IMPLEMEN-e TING A READINESS REVIEW PLAN AND PROCEDURES i 2 DEVELOP SCHEDULE FOR SUBMITTAL TO OCRWM FOR REVIEW AND APPROVAL l c IDENTIFY EVENT MILESTONES FOR PARTICIPATION BY STATES, NRC, eel, ETC.[c49. ,a,n,n,gg y 3 e 4 DEVELOP SCHEDULE FQR SUBMITTING PARTICIPANTS QA PROGRAM PLANS ANDI PROCEDURES TO WMPO e DEVELOP SCHEDULE FOR WMPO APPROVAL OF PARTICl-4 PANTS QA PROGRAM PLANS AND PROCEDURES e DEVELOP SCHEDULE FOR SUBMITTAL TO OCRWM AND ' NRC 5 e DEVELOP SCHEDULE FOR WMPO AUDITS OF PARTICl-PANTS QA PROGRAMS
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O T Y S R A M U . E N T I A J 5 Y G B N I E H T S E U L P P S M M N O O C C O I C D T A8 N 8 A C R9 A O1 F , E L 0 U E3 D L E U LY H DU C EJ H S M cY M T R sB R N E rM E E T- i T- M R uW sR E uC G L 9 P8 A sO N M9 E O I 1 N - L - e e
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SCHEDULE FOR MEETING REQUIREMENTS l U QA TO 1990 IMPLEMENT A FULLY QUALIFIED QA PROGRAM QUAUFICATON
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! NOV DEC JAN PROJECT LEVEL PtAMS
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4* LONG RANGE PLANNING EFFORT STATUS JULY 5, 1988 REX R. REUST
STATUS o PREPARING TO ACCELERATE PLANNING EFFORT o BASIS DATA FROM PREVIOUS EXERCISE DATA FROM WAS EXERClSE DATA AND NETWORKS FROM SCP EXERCISE o DEVELOPING PLAN AND SCHEDULE o PROJECTING THE WEEK OF 7/11/88 FOR KICK-OFF o THE SAIC TECHNICAL INTEGRATION GROUP WILL BE RESPONSIBLE FOR THE EFFORT INTEGRATORS AND SCHEDULERS WILL DEVELOP PACKAGES TRANSMIT INFORMATION TO PARTICIPANTS COORDINATE THE EFFORTS
l' , STATUS ICONTINUED_l o PARTICIPANTS NEED TO SUPPLY THE NAME(S) OF CONTACTS FOR THE EFFORT o THE PLAN IS TO HAVE PARTICIPATING ORGANIZATIONS INVOLVED EARLY o PRESENT PROPOSED SCHEDULE COMPLETE DECEMBER 1988 o DOCUMENT CONTROL UPDATED ONCE/TWICE PER YEAR SHOULD PROVIDE BASIS FOR PROJECT CONTROL i l l
i OVERSIZE l DOCUMENT ! PAGE PULLED I SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS ._. APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH FTS 492-8989
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