ML20024H595
| ML20024H595 | |
| Person / Time | |
|---|---|
| Site: | 05000605 |
| Issue date: | 05/28/1991 |
| From: | Poslusny C Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Russell W NRC |
| References | |
| NUDOCS 9106050349 | |
| Download: ML20024H595 (4) | |
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1 UNITED STATES
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NUCLEAR REGULATORY COMMISSION j \\ Gl
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May 28. 1991 Docket No. STN 50-605 MEr0RANDuti FOR:
T. Murley D. Crutchfield G. Holehen F, Mitc. glia J. Zwolinski B. Grires W. Russell H. Virgilio F. Congel J. Partlow W. Travers J. Roe
- f. Gillespie E. Butcher A. Chaffee S. Varga C. Rossi W. Boterian, EDO G. Lainas J. Richardson L. Plisco J. Calvo A. Thadani M. Slosson B. Boger L. Reyes, Ril Operatior.s Center THRU:
Chcries L. Miller, Director Cpt Standaroization Project Directorate Division of Advanced Reactors and Specie.1 Projects Office of Nuclear Reactor Regulation TROM:
Chester Poslusny, Project Manager Stendardization Project Directorate Livision of Advanced Reactors and Special Projects Office of Nuclear Reactor Regulatior,
SUBJECT:
DAILY HIGHLIGHT - MEETING WITH GEllERAL ELECTRIC COMPANY TO DISCUSS REACTOR SYSTEM BRANCH OPEN ISSUES FOR THE ADVANCED BOILING WATER REACTOR REVIEW DATE & TillE:
May 31, 1991 - 9:00 a.m - 1:00 p.rri.
LOCAT10h:
U.S. Ituuleet Regulatory Commission One White flint North, Room 10B11 11555 Rockville Pike Rockville, Maryland 20052 l
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- Docket File NRC PDR PDST R/F T. Hurley/f. Miraglia, 12G18 J. Partlow, 12G18 D. Crutchfield, 11H21 C. Poslusny T. Boyce L. Donate 11 T. Kenyon V. McCree D. Scaletti T. Wambact J.H. Wilstn J.N. Wil5)n R. Ranieri A. Chaffee, 11A1 OGC, 15B*t0 E. Jordan, MNBB3701 B. Grimes 9A2 Receptio sist, WF ACRS (l's), P-315 E. T =r & 12G18 P. O'Deil's, 12H3 Y. Overton, 12H3 L Plisco,12G18 P. Shea H. Rubin, 8E23 R. Jones, 8E23 G. Thomas, 8E23 C. Nichols, 801 J. Kudrick, 801 l
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s General Electric Company Docket No. SIN 50 60b 4.
cc:
Mr. Patrick W. Marriott, Manager J
Licensing & Consulting Services 4 -
GE Nuclear Energy 175 Curtner Avenue j
i San Jose, California 95125 Mr. Robert Mitchell General Electric Company 175 Curtner Avenue San Jose, California 95114 Mr. L. Gifford, Program Manager Regulatory Programs GE Nuclear Energy 12300 Twinbrook Parkway Suite 315 Rockville, Maryland 20852 i
Director, Criteria & Standards Division i
Office of Radiation Programs U. 5. Environmental Proter, tion Agency i
- 401 M Street, S.W, Washington, D.C.
20460 Mr. Daniel F. Giessing U.S. Department of Energy NE-42 Washington, D.C.
20585 Mr. Steve Goldberg l
Budget Examiner 725 17th Street, NW Room 8002 Washington, D.C.
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2 May 28, 1991 PAR 11CIPAN15:
NRC BNL General Electric C. Posiusny D. Diamond B. Huang D. Scaletti K. Valtonen V. McCree M. Rubin R. Jones j
G. Thothas C. Nichols J. Kudrick i
original signed by Chester Posiusny, Project Manager Standardization Project Directorate Division of Advanced Reactors and Special Projects Office of Nuclear Reactor Regulation tc: See twxt pale
- Meeting between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy "
43FederalRedster 28058, 6/28/78.
However, portions of this meeting may be closed to tiiTpWTc to protect General Electric Company proprietary information.
Members of the public who wish to attend should contact Chester Poslusny at (301) 492-1132.
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.I DATE$5p/91
$5h/91
$ 5Al/91 OFFICIAt RECORD COPY Document Name:
CHET DH
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4 May 29, 1991 t
Docket Nos. 50 373 and 50 374 MEMORANDUM FOR:
Richard J. Barrett Director Project Directorate !!!/2 Division of Reactor Projects. Ill/lV/V rROM:
Robert B. Elliott, Project Engineer Project Directorate 111/2 Division of Reactor Projects. Ill/IV/V
SUBJECT:
FDTHCOMINGMEETINGWITHCOMMONWEALTHED150NCOMPANY(CECO)
DATE & TIME:
Wednesday, June 5, 1991 8:30 a.m.
LOCA110N:
One White flint North Rockville, Maryland Room *. T 22 PURPOSE:
To discuss Ceco's approach to the IPE process.
See enclosed agenda.
- PARTICIPANTS:
NRC Utility B. Siegel D. Taylor et al.
L. 01shan R. Hernan J. Flack et al.
W. Beckner et al.
.d d BT Robert B. Elliott, Project Engineer Project Directorate 111 7 Division of Reactor Projects lil/lV/V
Enclosure:
Meeting Agenda cc w/ enclosure:
See next page
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy,"
43 Federal Register 28058, 6/28/78.
j OFC
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- S/bt/91
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OFFICIAL RECORD CDPY Document Name: CECO MEETING
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DISTRIBilTION Docket File NRC & Local PDRs PD111-2 r/f T. Murley/F, Miraglia 12G18 J. Partlow 12G18 B. Boger J. Zwolinski R. Pulsifer A. Hsia B. Siegel J. Hickman L. 01shan C. Patel R. Elliott A. Chaffee, EAB 11A1 OGC 15D18 E. Jordan MNCB 3701 B. Grimes 9A2 Receptionist OWFN R. Hernan 14C7 J. Flack et al. NLS324 M. Beckner et al. 10E4 ACRS (10) P-315 GPA/PA 2G5 E. Tana 12G18 P. O' Dell, 12/E/4 L. Plisco 10A19 R. Lobel, 17G21 J. Strasma, Region 111 C. Moore l
4 Mr. Thomas J. Kovach Connonwealth Edison Company CC:
Mr. William P. Poirier, Director V. S. Nuclear Regulatory Commission Westinghouse Electric Corporation Byron / Resident inspectors Office Energy Systems Pusiness Unit 4448 North German Church Road Post Of fice Box 3ES, Bay 236 West Byron, Illinois 61010 Pittsburgh, Pennsylvania 15230 Ms. Lorraine Creek Joseph Gallo, Esq.
Rt. 1, Box 182 Hopkins and Sutter Manteno, Illinois 00950 888 16th Street, N.W.
Suite 700 Mrs. Phillip B. Johnson Wast;ngton, D.C. 20000 1907 Stratford Lane Rockford, Illinois 61107 Pegional Administrator U. S. NRC, Region !!!
Douglass Cassel, Esq.
799 Poosevelt Road, Bldg. da 17 East Monroe Street Glen Ellyn, Illinois 60137 Suite 212 Chicago, Illinois 60603 Ms. Bridget little Rorem Appleseed Coordinater Attorney General 117 North L yden Street 500 South 2nd Street Essex, Illinois 60935 Springfield, Illinois 62701 Mr. Edward P. Crass Michael Miller, Esq.
Nuclear Safegut.rds and Licensing Sidley and Austin Division One first National Plaza Sargent & Lundy Engineers Chicago, Illinois 60690 E5 East Monroe Street Chicago, Illii is 60603 George L. Edger h
Newman & Holtzinger, P.C.
U. S. Nuclear Ailulatory Cornission 1615 L Street, N.W.
Pesident inspectars Office Washington, D.C.
20036 PR*1, Bnx 79 Braceville, Illinois 604C7 Connonwealth Edison Company Byron Station Manager Mr. Ron Stephens 4450 North German Church Road I
1111nois Emergency Services Byron, Illinois 61010
(
and Disaster Agency 110 East Adams Street 1111nois Department of Springfield, Illinois 62706 Nuclear Safety Office of Nuclear Facility Safety l
Robert Neumann 1035 Outer Park Drive Office of Public Counsel Springfield, Illinois 62704 l
State of Illinois Center 100 W. Randolph Commonwealth Edison Company Suite 11-300 Braidwood Station Manager Chicago, lilinois 60601 Rt. 1, Box 34 Braceville, Illinois 60407 Resident inspector U.S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242 1
4 Mr. Thomas J. Kovach Conmonwealth Edison Company Chairman Chairman, Ople County Board Will County Board of Supervisors Post Office Box 357 Mill County Board Courthouse Oregon, Illinois 610r-Joliet, Illinois 60434 EIS Review Coordinator Mr. Stephen E. Shelton Environmental Protection Agency Vice President Region V lowa-Illinois Ga', and
??0 5. Dearborn Street Electric Company Chicago, Illinois 60604 P.O. Box 4350 Davenport, Iowa 5280B Mr. J. Eenigenburg Plant Superintendent Mr. Richard Bax Dresden Nuclear Power Station Statiot Manager Rural Route #1 Ouad Cities Nuclear Power Station Morris, Illinois 60450 2?710 206th Avenue North Cordova, Illinois 61242 l'. S. Nuclear Regulatory Consission Resident inspectors Office Chairman Dresden Station Rock Island County Board Rural Route #1 of Supervisors Morris, Illinois 60450 1504 3rd Avenue Rock Island County Office B1dg.
Chairman Rock Island, Illinois 61201 Board of Supervisors of Grundy County Chairman Grundy County Courthouse LaSalle County Board of Supervisors Morris, Illinois 60450 LaSalle County Courthouse Ottawa, Illinois 61350 Phillip P. Steptoe, Esquire Robert Cushing Sidley and Austin Chief, Public Utilities Division One First National Plaza Illinois Attorney General's Office Chicago, Illinois 60603 100 West Randolph Street Chicago, Illinois 60601 Assistant Attorney General 100 West Randolph Street Chairman Suite 1?
111inois Commerce Commission Chicago, Illinois 60601 Leland Building 527 East Capitol Avenue l
Resident inspector /LaSalie, NPS Springfield, Illinois 62706 U.S. Nuclear Regulatory Commission Rural Route No. 1 Mayor of Zion F. O. Box ??4 Zion Illinois 60603 Marseilles, Illinois 61341 Dr. Cecil Lue-Hing V. S. Nuclear Regulatory Connission l
Director of Research and Development Resident Inspectors Office i
Metropolitan Sanitary District 105 Shiloh Blvd.
of Greater Chicago Zion, Illinois 60099 100 East Erie Street Chicago, Illinois 60611 Phillip Steptoe, Esq.
Sidley and Austin One First National Plaza Chicago, Illinois 60603
4
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MEETING AGENDA o
Progran. Plan o
Project Organization, Roles, and Responsibilities o
CECO Team o
IPE Partnership o
Technciogy Transfer o
Schedule / Integration of the Six IPEs o
Use of Detailed Technical Guidelines o
Integration of IPE with Accident Management Key Features of Technical Anproach (Overview) o o
Pealism o
Use of MAAP and TREAT o
Technical Review of the IPE Work Products o
involvement in Industry Programs l
o Status of Program to Date o
Subsequent NRC Meetings o
Topics o
Tentative Schedule i
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UNITED STAT ES l 3,,,
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hoply to:
301 East Stewart Ave.,
- 203 Las Vegan, Nevada 89101 Tel:
(702) 388-6125 FTS:
590-6125 TO:
Joseph Holonich, Acting Director, HLPD, M/5 4 H 3 FRDM Paul T.
Prentholt an4 John W.
Gilray Sr. On-Site Licensing Representativec DATE:
May 22, 1991 SUDJECT:
YUCCA MOljNTAIN PROJECT WEENLY HIGHLIGHTS Planne find enclosed the above-referenced report for the week of May 10, 1991.
There is nothing requiring specific manaaement attentien in this report.
nen ec w/entsr..:
Ling Stablein, M/S 4 H3 Harold R.
Denton, M/5 17 F :
Dean F.un i h i r o, Region 5
'4105310228 910522
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,y Yucca Mountain Site Characternation g
Project Office s8 D. O. Bos 98608 h'BS 1.
9 Las Vegas. NV 83193 8608 MAY 161991 John W. Bartlett, Director, Civilian Radioactive Waste Management, 110 ( FM-1) TOE.S OrrICE OF GEOLOGIC DISPOSAL WEEKLY HIGHLIGIITS FOR 'IllE WEEK ENDING MAY 10, 1991 I.
CRITICAL ITDI STAWS - YUCCA MO(UTAIN.3ITE Cl!ARACTERIZATION PROJLLCT (YMP)
A.
Site Characterization Planning
_Cxploratory Studies Facility (ESP'_ Tank Force Activities The YMP Project Manager presented an EST Activities Update at the May 1991 Office of Civilian Radioactive Waste Manactment (OCIMM)
Program Review.
OCIM! Milestone (M/S) status (See note)
The following milestenes/ activities have not been completed in accordance with their scheduled da',es as outlined in the IM-1 letter of February 12,1991, to W-20 and RW-30:
MILES MNE SCl!EDULED F:XPEC'IID DATE DATE ROA:
Prepare plan for resolution 3/15/91 5/15/91 of the Nuclear Regulatory Comission (NRC) Site Characterization Analysis Design Control Objection.,
- H1:
Issuance of a public doc'unent 2/91 TBD articulating the EST Decision Process.
H2:
Prepare transition plan from 3/15/91 TBD current document hierarchy to new document hierarchy Manage-ment System Improvement Strategy (MSIS).
YMP5
- _ _.. _..., _ _ _ _.. ~ _. _ _ __..
MAY 101991 John W. Bartlett MILESMIE SCI:EDULED EXPECTED DATE DATE H4:
Letter transmittal to the IIRC 3/31/91 5/24/91 informing them of implementation of the Design Control Process by OCRWM.
Note: At this time none of the above M/S appear to have a specific impact on portal construction.
- Milestone completion erroneously reported 5/3/91.
STAWS OF EST GDIERAL ARRA!GCHDir DRAWItGS
(./chitect/ Engineer Design Activities)
DELIVERABLE
!CRTl! AREA (81)*
SOUTl! AREA (86)
Mock Up 81*
39 Computer-aided draft design (CADD) 40 8
Check 10 6
I-D Review Quality Assurance (OA) Sign-off Moci Sketched to a completed, free hand drawing, then delivered to CADD.
CADD Computer-Aided Drawing and Design; produces finished drawing.
Interdisciplinary Review In-h'ouse review to ensure all aspects of drawing are covered. Disciplines include Civil, Mechanical, Mining, Structural & Architectural, and Electrical Engineering.
Chtnges in numbers reflect consolidation of two or more drawings into a single drawing.
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MAY I 61991 John W. Bartlett,
Site Characteriza'cion Plan (SCP) Progress Report (PR)
Input is currently being received and compiled by the Yucca Mountain Site Characterization Project Office (YMPO) for PR 4 (reporting period October 1, 1990, to March 31, 1991). A draft for YMPO review is expected to be produced by May 13, 1991.
SCP Consents A three-day Integration Group Meeting is being held this week in Las Vegas, Nevada, to continue review and revision of draft responses to comments in the State of Nevada's 1989 SCP comment package.
SCP Study Plan Status A revised text in response to comments was received from the U.S. Geological Survey for Study Plan 8.3.1.17.3.1, " Relevant Earthquake Sources." The text was sent to reviewers to determine if they feel a comment resolution meeting is necessary or whether we can go directly to comment verification.
A comment resolution meeting was held (via telephone conference) for Study Plan 8.3.1.9.2.2, " Water Resource Assessment for Yucca Mountain, Nevada."
SnIDY PLAN BREAK 1XEN In ReviFion After Screening Review.
1 In W.co and Headquarters (HQ) Review.
11 Awaiting Comment Rasolution Meeting 14 Awaiting Author Revision.................
9 In YMP0/HQ Verification Audit 2
Verification Complete-\\ waiting HQ Sign-off........
2 Awaiting YMPO Approval.
O Approved and Awaiting Transmittal to the NRC 4
NRC Acceptance Review 17 NRC Acceptance.
4 Total 64 Review of DOE-ApprcNed Study Plans No new items this week.
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4 John W. Bartlett Early Site Suitability Evaluation (ESSE)
The ESSE Status Briefing Package was presented to John Bartlett on May 9, 1991, in Washington, D.C., by Jean Younker, Science Applications International Corporation; Lawrence Rickertsen, Weston; and Bruce Judd, Decision Analysis, Inc. The package descrites the general site suitability methodology developed by the ESSF Core Team members and fulfills a milestone in the " Technical and M magement Support Services (T& MSS) Implementation Plan for Developing and Implementing a Method for Early Evaluation of Site Suit sility." On May 6, 1991, the Core Team members delivered to Jean Younker the 10 CFR 960 guidelines evaluations that were assigned.
B.
g irog g tp Pry ga g Environmental Ccmiplianco and Permitting A response was prepared to the Nevada Division of Environmental Protection's letter regarding YMP's ait quality permit application.
The letter requested information on the amount of acreage to be disturbed each year, dust control methods, and reclamation.
C.
Field Operations The Site Manager and YMP staff supported the YMP Open House and Site Tour on May 10, 1991.
YMP tour support was also provided to the Independent Cost Estimating (ICE) group and the Clark County Nuclear Waste Division.
The Site Manager received a request from the Nevada Test Site Office (NTSO) for the return of Joy 1 and Joy 2 drill rigs to YMP, should there be a need for them. Action is underway to respond to NTSO.
A Sample Overview Cotanittet Meeting was held on May 7, 1991.
D.
Project Planning and Control Input and rollup of participant data in the /lanning and Control System was completed to formulate the fiscal year 1991 PerforTaance Measurement Baseline.
E.
Quality Assurance (OA) Implementation i
The YMP Quality Assurance Committee Meeting was held on l
May 9, 1991, in Las Vegas, Nevada.
The meeting was attended by the Director of the Office of Quality Assurance, Yucca Mountain Quality Assurance Division (YMCAD) staff, and all participant GA Managers. Tophs of discussions and presentations included the following: OA Workshops, Grading Package Implementation, Quality Concerns Program, and Status of OA Program Document Revisions.
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MAY 161991 f
John W. Bartlett YMQAD Verification Group conducted surveillances on T& MSS and YMPO during the week of May 6-10, 1991. The surveillances were conducted to ensure compliance with the design control process.
The scope of the YMPO Surveillance included management review of System Requirements, System Description, Repository Design Requ!.rement, SCP Baseline, and Exploratory Studies Facility Design Requirement; Change Control; Training; and Records.
T& MSS was surveilled on the preparation and review of the Environmental Requirement Compliance Plan, SCP, Flowdown to Appendix J, Training, and Records.
A surveillance at Sandia National Laboratories was conducted on May 6-10, 1991, to review the areas of QA, Corrective Action, and Audits.
In addition, the ~urveillance t?am performed a corrective action verification on previously identified deficiencies.
YMOAD staff participated in the May 7, 1991, melting of the Quality Integration Group at Lawrence Livermore Nation,1 Laboratory. The group has been established to resolve scientif c quality issues / concerns.
This meeting was utilized to evaluate the possibility of rewriting Criterion 20.
The ne>t meeting of the group is scheduled for May 28-29, 1991, in Las Vegas, Nevada.
F.
Major Oversicht Group Meetinas No new items this week.
G.
Public Outreach Activities YMP public presentations were presented by YMPO on the following dates:
- Kenny Guinn Junior Hign School, May 3, '.991
- Community College of Southern Nevada (:lenderson Campus),
May 6, 1991
- Basic High School, May 7, 1991 H.
Near Term Decision Plan No significant change in milestone status from the last Program Management Meeting.
l l
MAY 161991 l
John W. Bartlett I.
Mana_ cement System Improvement Strategy _
YMPO remains concerned that it has not received MSIS draft products in accordance with the schedule developed by the Office of systems Compliance. A slip in the delivery dates of MSIS products could negatively impact the ICE and Energy Systems Acquisition Advisory Board reviews with subsequent delay in the resumption of ESP Title II.
II.
ANALYSIS & VERITICATION DIVISION Participated in the Site Characterization Integration Group Meeting to review / revise draf t responses to the State of Nevada's connents on the SCP on May 7-9, 1991, in Las Vegas, Nevada.
Participated in a meeting on perceptinn-based impacts and the Socioeconomics Policies and Requirements Document on May 8, 1991, in Washington, D.C.
Participated in the workshop to oegin drafting the Fourth Site Characterization Progress Repo.t. A preliminat,/ draft of Chapter 1 was completed on May 7-9, 1991, il Las Vegas, Nevada.
Participated in a meeting on May 9, 1991, in Washington, D.C., with Chris Henkel of Edison E'.ectric Institute, to discuss applicability to OCRNM of lessons learnea in the nuclear power industry.
Participated in the c<.manent resolution telecon on May 9,1991, for Study Plan 8.3.1.9.2.2.:
Water Resource Assessment of Yucca Mountain, Nevada.
III.
SIGNIFICANT ACCOMPLISHMENTS /INFORMATION ITEMS No new items this week.
IV.
UPCOMING EVDRS CALCiDAR Please note that the usage of "(P)" in the calendar indicates that the event is open to the public.
Date Event
. Location YMPO Contact l
A.
DOE /UQ Meetings l
- Thursday, Program Management Washington, C. Gert:
May 9 Meeting DC
)
MAY i 61991 l
John W. Bartlett
- I Date Event Location YMPO Contact B.
Internal and DOEAN Meetings
- Friday, Planning & Budget Las Vegas, C. Gert:
May 10 Meeting tN Wednesday, IN Manager's Las Vegas, C. Gert:
May 15 Program Review IN
- Tuesday, TPO Las' Vegas, C. Gert:
May 21 Meeting tN C.
NRC Inter _ actions TENTATIVE NRC Interactions Rockville, A. Sinnons
- Thursday, Scheduling Meeting MD May 30 D.
IMIRB Interactions (P)
Wednesday, WIPP Roundtable Albuquerque, A. Simmons May 15 Dry Run NM Monday-Risk & Perforrance Arlington, A. Simmons
- Tuesday, Assessment Panel VA May 20-21 Meeting
- Tuesday, WIPP Roundtable Washington, A. Simmons June 11 Discussion DC Tuesday-IWIRB EBS Workshop
- Denver, D. Harrison-
- Thursday, CO Giesler June 18-20 Tuesday-Joint SG&GAIG&G
- Denver, A. Simmons
- Thursday, Meeting on Testing CO June 25-27 Review Monday-SG&G Panel Meeting TBD TBD
- Tuesday, on ESF Design Review July 15-16 Update Tuesday-
!WIFB Full Board Arlington, A. Sinnons
- Thursday, Meeting VA July 16-18
MAY 161991 John W. Bartlett.
Date Event Location i
YMPO Contay D,
tWrRB Interactions (P) (continued)
Wednesday-Seismic Risk dalt Lake C0y, A. Simmons
- Thursday, UT September 4-5 Wednesday-Borehole Sealing Albuquerque, A. Sinnons
- Thursday, and Backfill tM,
September 18-19
)
l Tuesday-tMTRB Full Board Las Vegas, A. Sinntens
- Thursday, Meeting tu October 6-10 Tuesday-Site Suitability
'1BD A. Simmons Wednesday, ESF Design Review November 12-13 E.
Stato and Public Interact. ions (P)
- Monday, Clark High School Las Vegas, A. Robison May 6 tu
- Tuesday, Basic High School Las Vegas, M. Foley May 7 rn Wednesday, Bishop Gorman Las Vegas, J. Calovini May 8 High School NV Wednesday, CCSN-Henderson Henderson, A. Gil May 8 Campus Geology tN Classes
- Thursday, Community College of Las Vegas, A. Robison May 9 Southern Nevada IN
- Friday, Open House Tour May 10 Las Vegas, C. Gert:
NV
- Monday, Braggin' Rock Club Black Canyon A. Gil May-13 City, AZ
- Tuesday, National Assoc.
Las Vegas, Various May 14 of Accountants IN Wednesday, Faye Herron Las Vegas, E. Harle May 15 Elementary School tN i
I
t MAY 161991 John W. Bartlett Date Event Location YMPO Contact E.
State and Public Interactions (P)
(continued)
- Thursday, U.S. Council for Washington, C. Gertz May 16 Energy Awareness DC
- Thursday, Beatty Information
- Beatty, C. McKnight May 16 Of fice-ABC's of tN Radiation
- Monday, Project Update
- Pahrump, C. Gertz May 20 Meeting IN
- Tuesday, Project Update Las Vegas, C. Gertz May 21 Meeting IN
- Thursday, Project Update
- Reno, C. Gertz May 23 Meeting IN
- Thursday, MENSA Las Vecas, A. Robison May 23 IN Wednesday, BurkholderiJunior Henderson, G. Fasano May 29 high School IN Wednesday, ANS '91 Annual
- Orlando, C. Gertz June 5 Meeting FL
- Saturday, Open House Tour Las Vegas, C. Gertz June 8 IN spt arl P. Gertz YMP:DLH-3712 P'roject Manager CC:
H. H. Brandt, HQ (RW-13) FORS J. C. Bresee, HQ ( p 10) FCRS S. J. Brocoum, HQ ( % 22) FORS B. A. Corny, HQ (RN-14) FORS M. A. Ferguson, HQ ( % 5) FORS Stephanie Hannah, HQ (PA-3) FORS
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NUCLE AR REGULATORY COMMISSION WASHINGTON, O C. 20555 g, ' u,#
Reply tot 301 E. Stewart Ave.. 44203 Las Vegan, NV 89101 Te'-
(702) 389-6125 FTS:
598-6125 tL E._J1 Q_R_hjLD_U_t1 DATE:
May 20, 1991 FOR:
Joseph Holonich, Acting Director. HLPD, Division of High-Level Waste Manacement, 11 / 5 4 H3 FROM:
John W.
Gilray, Sr. OR - YMP
SUBJECT:
YMP Site Report for the months of March and April, 1991 1.
QU A',. LT Y ASSURANCE A.
5t.atus of YMP QA_Worichops e
- 06. Grading _Worh@gp In March of 1991 the YMPO recuentec tnat t.
workchop ue nelci on the OA grading procer The coals of t hre wo m.aa m,re to identify specific problems with the OA cracinq
)- o c c.s e and to develop recommendations for.i m o ro vi n a
- t. h e G4 a ra:.:ing process.
[
Phace one and two of tne warkshoo were neld at Ln; Vecer April 2 throuah 3 and April 16 c.n d 19 1%i. rennec*uvel;.
The overall problem statement developed at this worksnoo 1
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with involvement from all YMP participants was defined as-follows:
The process for preparing grading lists, grading packages and-defining grading controls, including purpose (a) is not clearly defined, (b) lacks clear guidance and training (c) is too cumbersome and (d) is too slow and costly.
The workshop members attributed the causes of ttW grading problems tot 1.
Current grading process is too complex and does not provide clear guidence.
- 2. Lack of consistent interpretation and definition of purpose, terms, Regs, & DOE orders.
- 3. Process requires OA grading for administrative activities and non-quality affecting items and activities.
4.
Inappropriate management direction.
The workshop members concluded that the upper YMP management must be involved in establishing a clearer policy statement and guidance for the grading process for quality affecting items and activities that meet regulatory requirements.
The workshop recommended that the OA grading process not apply to non-quality related items and activities such as project control, administration, management, preliminary and scoping activities.
The YMP management accepted the overall' findings of the OA grading workshop and committed to study the lessons learned from the grading process and initiate actions to modify and simplify the overall grading process and related procedures.
A detailed action plan is under development to accomplish identified tasks and to establish dates for follow-up meetings.
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The YMP OA Grading' Workshop report, which explains in detail the results of this workshop, has been sent to HLPD/OA (K. Hooks) under separate cover by this office.
4 O A _Mgr_L s ho p.And So f twa rle.
Based on the recommendation from the Software Workshop a projectwide Software Advisory Group (SAG) has been established to oversee the actici 6 underway to improve the overall OA software program.
18.s first meeting of the SAG was held April 24-25, 1991, in Las Vegas, Nevada.
The SAG group reviewed, revised, and finalized their charter and presented-this to YMP management for acceptance.
(The charter is addressed-in Enclosure 1).
The following is a list of SAG Members:
Claudia Newbury, YMP, Chairperson John Matras, Science Applications International Corporation (SAIC), Recording Secretary Stephen Bauer, Sandia National Laboratories Daniel Gockel, U.S.
Geological Survey Russ Hilsinger, Raytheon Services Nevada (RSN)
Teresa Quinn, Lawrence Livermore National Laboratory Bruce Robinson, Los Alamos National Laboratory Christine-M. Thompson, Reynolds Electrical &
Engineering Co.,
Inc.
Albert Williams, YMP The first task of the SAG is to revise the OARD Section 19 by July-31, 1991.
The schedulu of SAG meetings for accomplishing.this task is as follows:
May 16-17 at Las
(
l Vegas.
The agenda for-the May 16-17 meeting is (a) review l
status items, and (b) initiate rewrite OARD Section 19.
In regards to the scheduled May 16 and 17 SAG meeting, Raytheon is bringing their Missile Systems Division Software OA 3
~
~.
personnel from Connecticut to discuss their controls in the development, qualification and controlled use of their software.
I will be attending this meeting and will provide the results of the Ratheon presentation and other issues to NRC/HLPD OA (K. Hooks). Meetings are scheduluo for June S-7 at Albuquerque; June 19-21 at Denver; July (week of 7/29' at Las Vegas.
During the Week of July 29 SAG will finalize changes to CARD, anc present results to management.
The SAG believes that the following concerns and problems must be addressed in the revision of Section 19 of the OARD.
1.
That iterative development and rapid prototyping are acceptable in the software lifecycle.
2.
Clarification as to when documentation is placed under conf igur ation management.
3.
Clarification of the requirements of Section 19 on commercial codes (operating systems, Lotus, compilers, word processors, etc.).
4.
Some of the requirements of NUREG-0856 are obsolete as applied to the present art of developing code (e.g.,
flow charts, block diagrams, variable lists, etc.).
S.
Clarify the need for Verification and Validation (V&V) schedules in Section 19.
6.
The requirement for V&V planning needs clarification.
7.
Clarification as to when acquired codes fall under Section 19.
4
i 8.
Section 19 needs to address more flexible controls for lifecycle through clarification of minimum documentation, reviews, and verification activities.
9.
Consintency in the use of the word a rt o l i c a t i on.
- 10. The need for independent V&V.
B.
tii s ce ll_an gous.
OCRWM has posted the job announcement position for the YMP OA Division Director recently vacated by Don Horton.
The closing date for receiving applications for this position is May 29, 1991.
A copy of this announcement is enclosed for information.
(Enclosure.' ).
4 I will be assisting Teek Verma (HLPD/OA) in ooserving the YMP audit (No. YMP-91-05) of USGS the week of May 20. 1991.
The audit team will evaluate the effectiveness of USGS CA Program requirements and implementing procedures.
In addition, implementation of corrective action (s) as provided in the response (s) to open Project Office Standard Deficiency Reports will be evaluated and, if found satisfactory, will be closed.
The technical specialist of the audit team will audit activities associated with (1) i Unsaturated Zone Hydrochemistry, (2) Site Saturated Zone Ground-water Flow System, (3) Quaternary Regional Hydrology, and (4) Historical and Current 5'eismicity.
The evaluation of these above activities will include a determination of adequacy of technical qualifications of l
scientific personnel, the understanding of procedural l
requirements as they pertain to scientific investigation activities, the adequacy of technical procedures, the i
development of study plans, and work supporting the Site Characterization Plan.
5
1
+
Under the direction of John Bartlett an independent management assessment of the OCRWM and YMP activities and QA program has been performed.
A formal report is in preparation and should be available for review by mid June.
a The YMP is restructuring their DA audit policy whereby they will rely on a series of mini audits and surveillances of participants quality related activities rather than performing yearly large scale audits.-
YMP OA program procedures will be revised accordingly and be in effect in the near future.
+
YMP OAD_Syr_vfillpnge_,_q1_losJ iamos The YMP QAD conducted a surveillance, No. YMP-SR-91-Oi4, at the Los Alamos Test Manager's Office (TMO) office in Las Vegas, Nevada, and in Los Alamos, New Mexico, on April 15-25, 1991.
Based on the surveillance results, i t was determined that the Los Alamos OA program is being i
satisfactorily implemented in the criteria examined.
There were no Corrective Action Reauests i sued as a result of l
this surveillance.
o YMP O AD_S.u rvell_l a n ce_of_USQS As a result of YMP OAD surveillance, No. YMP-5R-91-Oi2 of USGS, Don Horton has notified Dwight Shelor that the remaining exception, " Personnel-Qualifications" for the OCRWM acceptance of the USGS GA' Program has been resolved.
This' surveillance was performed to evaluate implementation of the USGS procedure governing the development and conduct of training and the qualification and certification of personnel to perform quality-affecting activity.
The
' surveillance verified that the Privacy A c 4, issues, and Personnel Qualificationn related to the OCRWM exception, have been adquately resolved.
Also during this 6
l l
9 e
4 surveillance, corrective action for related Standard Deficiency Reports (SDRs), 143, 145, and 331 were verified and subsequently closed.
Based on this information, the OCRWM Office of Quality Assurance concludes that the USGS OA Program is acceptable for implementation of new site characterization activities and other quality-related activities for the Yucca Mountain Site Characterization Project with no exceptions.
II.
WASTE PACK 6GE The LLNL February, March, and April monthly status reports are enclosed (Enclosure 3).
It is encouraged that comments and/or questions regarding the contents of these reports be directed through this office for action and resolution in order to minimize the impact on the YMP.
There are no new issues that this office has identified that have not been brought to management's attention.
cc w/encs K.
Hooks, M/S 4H3; R.
Ballard. M/S 4H3; J. Latz wo/ enc:
D.
- Shelor, C.P.
Gertz, R.E. Loux, M.
- Glora, G.
- Cook, D.M.
- Kunihiro, D.
- Weigel, B.
Youngblood, J.
Linehan, M/S 4H3; H.
- Denton, M/S 17F2, R.
Bernero, M/S 6A4; H.
- Thompson, M/S 17G21; S. Gagner, M/S 2GS; C. O'Donnell, M/5-NLS260 7
1
.----c
.y-a DCDSURE 1 YUCCA MOUtTIAIN SITE CHARACTERIZATICU PRCATECT (YMP)
SOPIWARE AWISORY GROUP (SAG)
O!ARTER OBJECTIVE contribute to the evolution and implementation of a software nanagement o
program that:
1.
rakes optimum use of standard software engineering practices 2.
is compatible with accepted scientific and engineering practices; 3.
ensures that the products of Yucca Mountain activities will support the licensing process; and 4.
provides a coherent and stable environment for software development and use.
Provide advice and consultation to the U.S. Department of Energy, Yucca o
Mountain Site Characterization Project Office (YMPO) on software-related matters.
Facilitate communication, discussion, and resolution of software-related o
concerns arising from maiagement, quality assurance (OA), or technical staff on YMP.
APPROAQ1
'Ihe SAG shall foster comunication and resolution of software issues by:
Initiating activities to improve comunication and to produce integrated o
solutions to software-related problems.
Subnission of observations, recommendations, and proposed courses of action o
to the YMPO Project Manager or designee, and QA Manager or designee.
Copies shall be forwarded to the Technical Project Officers (TPOs) and each member.
Serving as a sounding board for identifying problems, discussing issues, o
and proposing solutions to software-related concerns that may have broad programmatic implication, are interdisciplinary in nature, or could impact multiple activities and organizations.
Emphasis will be on innovative improvements that could positively impact the technical direction or scope of the YMP activities.
S m_-
/
MEMBERSHIP The mPO will have SAG Chair responsibility. TPos will select members from their staff and and take into consideration such factors as diversity and representation of viewpoints and disciplines and breadth of understanding of the program and goals of mP activities. The SAG Chair will have responsibility to ensure that all appropriate disciplines are represented.
Representation should consist of technical staff, software engineers, QA personnel and nanagement.
Each participant will have one voting member.
b A SAG secretary will be assigned by the Chair to coordinate preparation of the agenda, distribution of meeting minutes, and other administrative matte.ts.
The SAG will evaluate meeting and membership effectiveness on an annual basis.
Membership will be rotated on a pericdic basis.
MEETINGS Frequency and Location-The SAG shall meet at least quarterly.
Business will only be conducted when a quorum is present.
A quorum will consist of 75 percent of the voting members. Meeting sites will rotate among the SAG member home sites.
Agenda-The SAG shall follow a formal meeting agenda. A summary of the previous meeting topics and list of proposed agenda items will be distributed at least two weeks prior to each meeting.
Participation-The SAG may invite experts il various disciplines f rom within or outside the mP to participate in meetings and t. advise on the topics under consideration. WP staff memba s are encouraged to provide input to the SAG.
SIGWIUPIS:
h:
$ 1L 1l C
P. GertW YMPO Project Manager
' Dat'e
~
Yl Dona [d G.
ott6ttf Director QA Division Cate DW 2- & ln lAaudia M. Newbury, MP SAG Cha,i# person
/
Dhte
G w (AtrevAk ?~ j
.Mcr# Promotion Mail Distribution Code: 1G 20 30 4W 50 Vacancy
~
05-ofA l 0% N-91
-Announcement lasse Date :
Cnosing Daie :
Area of Consee emn: 1 o Fist T.or Org :
2 D DOE Y struawn U.S. DEPARTMENT OF ENERGY a o Commums ues (smus Cmes Onm a o oot utenme
$ n Namnwee: (Status /knetatus CarWdates)
_ _.. =. _ _ _
PC$1 TION: Supervisory General Engineer. C&B01-15 NO.0F POV.aONS SALARY RANGE: H l. 64 3 - 8 80.138 Per annu" ORGANIZATION LOCATION-Office of Civilian Radioactive vaste Management, of fice of Quality Assurance. Yucca PROMOTION POTENTIAL:
O To GS-G No Known Nuntain Project of fice Quality Aasutance Divisica BARGAINING UNIT POSITION: O Yes 3 No SUBJECT TO PMRS:
3 Yes C No GUPERVISOR/ MANAGER:
G Yes* O No OEOGRAPHIC LOCAT10N. Las Vegas, kevada
- Newey appointed supervisors / managers must serve a one year probaborww penod.
--_1 DUTIES AND MSPONSIBluTitS. Plans. Supervises, and direc ts all activities of the Yucca Mountain Quality Assurance Division (YMOAD). Establishes priorities, deadlines, and goals. Assigns work; evaluates progress; identifies trateing and developmental needs, and develops and directs technical training requirements and programs for on-the job t ra i ni r.g of personnel. Manages and directs the YMQAD and participates in development of the organitation's Quality Assurance (t)H Program. Provides guidance, review, and accroval of project participants' QA program plans and oversight of prc edures and activities. Evaluates activities to enhance research and development methods processes, and ovality verification methods that contribute to improvements in quality me' hods, construction sededs and technical perf orm a nc e s.
Evaluates requirements for major program changes, and recommends thee to the Of fice Director, Develops and saintains effective communications and liaison relationships with various federal organizations at the national and local levels, such as the Nuclear Regulatory Commission (NRC). !!.$. Geological Survey, etc. regarding project quality plans, activities. Short and long-term goals and object..es. Directs the formulation, development, analysis, reviev, and preparation of budget assumptions and submission for the Division, and for assigned responsibilities.
QUALIFICATION REQUIREMENTS: Apsacants rnust haws generat specthc. and specahaed esponence s.: coscribed t.eaow. This recunemom is in accor-cance with the OPM Mancboca X.118. avsdaDie for renew in your goescnne: offica, which spec! Lea when and how e& canon may to subsMoo lot en pSnence, When specihed, appdcants rnust also meet the $elocuve Piacement Factars Ested t>eiow SASIC RE0V!REMEwfS: Candidates must show successful completion of the reavirements described in either A or 6: (A) A full 4-year course of study in an accredited callege or university leading to a bachelor's or hiper degree in enginsering; OR (8) Appropria te cornbination educa tion and encertence.
$PECI ALIZED EXPERIENCE: In addition to the basic requirements, candidates must have one (1) year of specialized experience which is in or directly related to the line of work of the position to be filled ano which has todoped the applicant with the particular knowledge skills and abilities to successfully perform the dutitt of the position.
To be creditable, speciali!ed experience must have been at least tow 1valert to the nest lower grace level in the normal line of progression for the occupa tion in the organ) ation.
elANMNO F ACToes: Appucanis wno meet the quauticanon reaw monts oescrtceo ecove wm t,e lunhar evaivateo io ceterrmne me sitent to wiucn Hiea educahon, wort, related esperience, training, eaarcs and snerosory appraisais indica:o they possess or have the potent.at to scrwiri knowedge, suhs.
aWet. and personal charactertsuca regulred to perform the duties and responalbillt:es descnood above.
L personnel management concepts, and motivate and develop employees. Ability to com
, utiltre 2.
Skill in the develo;nent of a cuality assurance program involved in nuclear waste activities.
L Ability to organite, plan, schedule, anit suce vise the conduct of audits and surv 4
e.
5.
Ability to understand and support Eaual OpporWotty Program plans; use position s:anagement ennronment free of discriinanation and sexual harassment. employment and training programs techniques and special VOLUNTEERS FROM THE PEACE CORPS AND VISTA WHO A PLEASE SPECIFY ELIG;BILITY FOR SUCH APPOINTMENT.
WHEN APP ( Y!NG, All RANK!NC TACTOs; Vitt BE WE1CHED EOUALLY Applications will'oe accepted from severely handicapped app:1 cants, certain Vietnam fra and disabled veterans volunteers from the Peace Corps and Y15TA who are eligibit for appcintment under please DecMfy for such employment.
special authorities. When applying, TO APPLY: For each announcement under wruen appucation is me::e. submit :he lothwing: (a) current completed "Ap SF.171. with ornginal scature. (b) completed "Superwsory Appraiss! of Potental Fortormance" k and on rev r
p oyment" saats and abiuues as iney reiste to i:ee raniong factors,(dj curroni parformance apprarsai of recoro and (e)" Request hr M HQ F 3335.1 CASS). The SF.171 should include all pertinent nagartence. awards, cunmeendons. training and any other per ciuda posinon desenpuons. RankHis will be casod on informonon contained in the appucant's SF.171: the Superv rmation. Do not in.
appi6 carts elatornent of krmwindgo, eklue and abuiuoe: cu* runt purformance appratsat and any other renovant documenta outrmine CC#VERNMENT ENVELOPES WILL NOT DE ACKNOWLEDGE 0 08 CONSIDER y uiu uppneani Ar CLOSING DATE. They should bu eunt to tt o U.S. Deparhaunt of Eno'Dy.1000 Independence Ave., SW Rarm 4H-09 tp_ 20585. n e necessary ferms m f* * *
- dd~ ~
~M
~~
-._.._..~.--u,._a
-._..._m_
H6adquarters opsratione support crcnch-bepartment of Enargy Washingtsn, D,c. 20585 SUPERVISORY APPRAISAL OF POTENTIAL PERFORMANCE PLEASE HAVE THIS APPRAISAL COMPLETED BY YOUR, SUPERVISOR Announcement No.:2 71" AND SUBMIT IT WITH YOUR APPLICATION. SF-171.
Position:.lanniam.nettui ruin n.
CM-802 15 Name of Applicant:
Basis for Appraisal Level of Potential _
Perforrnance Check One Please check (A x
RANKING FACTORS as appropriate:
c.
i e
c 5
? Ee.i (Knowledges, skills, abilities, and personal characteristics) 4 Exceptional
,( ][ $
4 s. Superior 2
- 2. Satisfactory 53 g
.3 et E
1' Week
$ O$ 'o O None o
4 3
2 1
0 1.
Ability to communicate effectively with management and employees, delegate authority and responsibility. utilise perst>nnel management concepts, and motiva te and develop ew,loyees.
2.
Skill in the developsient of a quality assurance program involved to nuclear weste activities.
3.
Knowledge of pertinent Nuclear Regulatory Commissten policies and procedures pertaining to quality assurance.
4 Ability to organize, plan, schedule, ar'd supervise the conduct of audits and surveillances.
5.
Ability to understand and support Er.uel Opportunity Program planet use position sanagement techniques and special emplovmont and training
-programs to improve prospects for tho' handicapped.-women, and minoritiest and amintain a working environment f ree of discrimination and sexual Aare s sswr>
NARRATIVE: Please include any other information pertinent to the applicant's potential knowledge, skills or abilities and personal characteristics that may not be adequately axpressed above.
(Attach additional sheets if needed.)
IN WHAT CAPACITY ARE YOU MAKING THIS APPRAISAL? (Phase - as appropriate)
C Present immediate Supervisor Present 2nd Level Supervisor Other (spec /fy)
Former immediate Supervisor C Former 2nd Level Supervisor Period Covered by this Appraisal:
From:
To:
Appraiser:
(Signature)
(Detal (Phone No.1 (11 this appraisal la submitted directly by the appraiser. the applicant, upon request, will be permitted to rev[ew and obtain a copy of It.1 DOOF V001(6 41)
E wc\\. m '3_
Lawrence Livermore National Laboratory
'U LLYh1P9103006 WBS 1.2.9 March 13,1991 "OA: N/A" Carl Gertz, Project hianager Department of Energy Yucca Mountain Project Office P.O. Box 9S518 Las Vegas, Nevada 89193-8518
SUBJECT:
Yucca Mountain Project Status Report - February 1991 Attached is the February Project Status Report for LLNL's participation in the Yucca Mountain Project.
If further information is required, please contact Elizabeth Campbell of my staff at FTS 532-7854.
Sincerely, e'
A
.N /,
e Leslie Jardine a
3v LLNL Technical Project Officer for YMP LJJ/EC/ec cc:
Distribution I
DISCLAIMER The LLNL Yucca Mountain Project cautions that any information is preliminary and subject to change as further analyses are performed or as an enlarged and perhaps more representative data base is accumulated.
These data and interpretations sho ald be used accordingly.
_.._g.
g., g._ _,,c,.s..s g.x, - o.., w v. r,.. -.,,.., e ~ n.e. # n w.o m,,n,_.,
l LAWRENCE LIVERMORE NATIONAL LABORATORY YUCCA MOUNTAIN PRO MONTHLY TECHNICAL HIGHLIGHTS AND STATUS REPORT FEBRUARY 1991 TABLE OF CONTENTS 1,2.1 Systems WBS 1.2.1.1 Management and Integration (Ballou)
WBS 1.2.1.2.4 Systems Engineering implementation (Revelli)
Performance Analyses (Chesnut)
WBS 1.2.1.4.2 Waste Package Performance Assessment (Chesnut)
Geochemical Modeling WBS 1.2.1.4.5 Geochemical Modeling & Database Development (Wolery/ Johnson) 1.2.2 Waste Packace WBS 1.2.2.1 Management and Integration (Ballou)
Waste Packace Environment (Wilder)
WBS 1.2.2.2.1 Chemical & Mineralogical Properties of the Waste Package (Wilderl WBS 1.2.2.2.2 Hydrologic Properties of Waste Package Environment (Chesnut)
WBS 1.2.2.2.3 Mechanical Attributes of the Waste Package Environment (Blair)
WBS 1.2.2.2.4 EBS Field Tests (Wilder)
Waste Form & Materials Testing (Stout / Clarke)
WBS 1.2.2.3.1.1 Waste Form Testing - Spent Fuel (Stout)
WBS 1.2.2.3.1.2 Waste Form Testing - Glass (Bourcier)
WBS 1.2.2.3.2 Metal Barriers (McCright)
WBS 1.2.2.3.4.1 Integrated Radionuclide Release: Tests and Models (ten Brink)
WBS 1.2.2.3.4.2 Thermoaynamic Data Determinauon (Silval Encineenna & Systems Analyses (Ruffner/ Clarke)
WBS 1.2.2.4.1 Waste Package Design WBS 1.2.2.4.2 Container Fabrication & Closure Development (Clarke)
WBS 1.2.2.4.3 Container / Waste Package Interface Analysis (Ruffner) 1.2.5 Reculatorv and Institutional WBS 1.2.5.2.1 NRC Interaction Support (Blink)
WBS 1.2.5.2.2 Site Characterization Program (Ballou)
WBS 1.2.5.2.4 Technical Support Documentation (Blink)
WBS 1.2.5.2.5 Study Plan Coordination (Ballou)
WBS 1.2.5.2.6 Sem1-Annual Progress Reports (Blink) 1.2.9 Project Manntrement WBS 1.2.9.1.1 Management (Jardine)
WBS 1.2.9.1.4 Records Management (Bryan)
WBS 1.2.9.2 Project Control (Podobnik)
WBS 1.2.9.3 Quahty Assurance (Dann)
-t LAWRENCE LIVERMORE NATIONAL LABORATORY (LLNL)
YUCCA MOUNTAIN PROJECT (YMP) STATUS REPORT FEBRUARY 1991 1.2.1 SYSTEMS 1.2.1.1 Management and Integration Staff attended a software QA workshop in Las Vegas on February 4-7 which provided an open forum to identify problems with the present SQA system and to initiate development of recommendations for improvement.
1.2.1.2.4 Systems Engineering implementation Staff participated in the Physical System Functional Analysis and the start-up of the MSIS ESF Mission and Functional Analysis activity in Denver, February 4-8.
Staff participated in the Physical System Functional Analysis integration meeting in Las Vegas, February 19-21.
1.2.1.4.2 Waste Package Performance Assessment Staff participated in a Partition and Transportation Meeting held in Pleasanton, CA on February 11. A telecon was held on February 13 to discuss the Performance Assessment role in this area.
Source term development is continuing.
Work continued on completing the PA problem definitions and work planning for PA support to the site suitability effort.
A conference abstract by T. Ueng and W. O'Connell entitled " Diffusive Barrier Simplified Applications" was prepared for the Focus '91, Nuclear Waste Packaging Conference to be held in Las Vegas, September 29-October 2,1991.
Staff reviewed the draft System Functional Analysis for function 1 A, " Dispose of Waste", prepared by the Systems Engineering Working Group.
Review effort focused on functions 1 A.2, Isolate Waste and 1 A.3, Evaluate System Performance.
Work continues on the SNL/LLNL MOU for the Near Field and Engineered Barrier System Scenario Determination Task.
1.2.1.4.5 Geochemical Modeling and Database Development Updated the SUPCR:~91 subset of GEMBOCHS to incorporate recently revised thermodynamic data nnd equation-of-state coefficients for 61 aqueous metal complexes.
piI k.
L Located and resolved a subtle D00UT bug that resulted in the calculation of erroneous dissociation constants for six aqueous diphosphate complexes (K, NalP207 and (Na2, Ca, Mg, Sr]P207, as written to DATO.com.R9. (The R10 suite of DATA 0 files, to be generated in March, will include corrected dissociation constants for these species together with revised dissociation constants for the aforementioned SUPCRT91 aqueous metal complexes.
The document by J. Delany and S. Lundeen entitled "The LLNL Thermochemical Database and Revised Data and File Format for the EQ3/6 Package" will soon be submitted to YMPO for approval.
Viewgraphs were generated summarizing current and future modeling capabilities of the CEMBOCHS thermodynamic database for inclusion in a talk to be given at the Pittsburgh Conference in Chicago, March 4, by T. Wolery. The talk is entitled "EQ3/6 Software and its Applications to Environmental Problems".
Generated WAS input for WBS 1.2.1.4.5, Geochemical Modeling, which encompasses maintenance and development of the GEMBOCHS database, associated sof tware, and the EQ3/6 package.
This input provides a summary or accomplishments in FY90-91 as well as projected accomplishments in FY92 and beyond.
Work continued on writing and revising EQ3/6 code documentation.
1.2.2 WASTE PACKAGE 1.2.2.1 Management and Integration Staff attended a software QA workshop in Las Vegas on February 4-7 which provided an open forum to identify problems with the present SQA system and to initiate development of recommendations for improvement.
1.2.2.2 Waste Package Environment Chemical and Mineralonical Prormrties of the Waste Packace Environment Revisions and additional contributions were submitted to the Near Field Environment Report.
Technical plans and background material for the joint AECL/ DOE Fundamental Materials project were reviewed with A. Meike and W. Glassley in preparation for the Feb. 27-Mar.1 meeting.
Staff repeated a series of EQ3/6 simulations to be described in the UCID entitled
" Progress in Modeling Fluid-Rock Interaction at Yucca Mt, Nevada", currently in preparation. The original simulations had been made over the past year using a number of different versions of the codes and data base. To ensure consistency among the results, common versions of the code and database were used for the LLNL-February Status Report 3/13/91 1
calculations in the report. The calculations of the impact of water chemistry on rock-water interactions were also expanded to include Eh-pH conditions in equilibrium with the atmosphere, in addition to those Eh-pH conditions measured in waters from Yucca Mt.
Staff are developing a solid solution model based on the Vanselow exchange convention.
This model will allow simulation of precipitation / dissolution of clinoptilolite (and other exchangers) according to the Vanselow convention. LLNL has previously shown that adsorption of Cs and Sr on clinoptilolite is best modeled using this approach.
The HP HPLC (liquid chromatograph) was received. Also received were the Waters conductivity detector and an ADC (analog-to-digital converter) to allow ion chromatograph (IC) analyses as well as liquid chromatograph (LC) analyses with this instrument. Installation will be completed next month. These two instruments will allow study of the effects of organic aqueous species on the inorganic aqueous species and minerals of interest to not only the Geochemistry / Mineralogy Task, but also the Man-Made Materials Task. Inorganic aqueous anion analyses will now be possible and should significantly improve the electrical balance calculations, particularly for higher temperature runs. These electrical balance calculations are used as a measure to evaluate the analyses.
Man-Made Materials A change request to add Man Made Materials as a separate WBS element 1.2.2.2.5 has been submitted to the Change Control Board.
Hydrolocic Properties of the Waste Packace Environment Calculations have been conducted investigating fracture-matrix flow from the ground surface to the repository horizon and on to the water table. For example, for multiple, contiguous 100 nm fractures (assumed to penetrate the entire thickness below the repository) and ponded water at the repository horizon, the wett ng front-i moves from the repository horizon to the water table in about 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> in roughly 50% of the area where nonwelded vitric CHnv is not present below the repository and in-about 290 days in the area where CHnv is present. For similar assumed fracture morphology and ponded water at the surface, the wetting front moves from the surface to the repository horizon in about 56 years (70 to 10,000 times longer than the travel time below the repository)
These calculations have two important implications. First, the calculations can be used to determine the combinations of idealized fracture morphology, matrix properties, and water ponding duration which appear to meet regulatory limits on release rates and ground water travel time, particularly as consequences of the PA human intrusion scenarios that directly l.
inject water into the repository horizon.
Second, the calculations show that
[
quantifying both fracture and matrix properties in the rock above the repository horizon is required to calculate its effectiveness as a barrier limiting the amount of water reaching the engineered barrier system. The acceptable combinations of fracture morphology and ponding duration above the repository will probably be less stringent than for below the repository.
LLNL-February Status Report 3/13/91
-=
Work continued cn the fracture healing study.
The water samples that were collected _ from the steam-flow experiment in January were analyzed. The silica concentration in the water condensed from the steam that flowed through the sample ranged from 20 to 50 ppm compared to about 3 ppm in the water before antering the sample. A blind test has been run, using an Al sample to replace the roch.x.mpie, m verify that the source of the silica in the water condensed from the steam was actually from the rock sample. The water samples collected in the blind test are being analyzed. The rock sample is being prepared for SEM analysis of the fracture surfaces before and after the experiments.
A prototype enhanced version of V-TOUGH has been completedivhich produces efficient and very flexible time histories of all primary and secondary variables calculated by the code. This capability will enhance _ data extraction from V-TOUGH output and will reduce storage requirements for output. Enhancements have also been added to thi.= prototype including the capability of accommodating time-dependent Dirichlet boundary conditions.
The first draft of the revised study plan for the Laboratory Near Field Hydrology Task ir about 90% completed.
An abstract by W. Lin entitled " Role of Steam in Fracture Healing of Topopah Spring Tuff Sample" was submitted to the American Geophysical Union (AGU)
Spring Meeting to be held in Baltimore, MD, May 28 - June 1,1991.
Mechanical Attributes of the Waste Packace Environment Continued to revise the Study Plan for Characterization of Mechanical Attributes of the Waste Package Environment (Study Plan 8.3.4.2A.3) incorporating the review comments received.
EBS Field Tests /ESF Test Desien Work continues on the first draft of the Near Field Environment Report.
The report by A. Ramirez, et al., entitled " Prototype Engineered Barrier System Field Tests (PEBSFT) - Final Report" was submitted to YMPO.
Staff reviewed the University of isevada, Reno proposal by G. Danko entitled
" Application of Long Horizontal Cooling Enhancement for a Nuclear Waste Repository"in Las Vegas on February 7.
1.2.2.3 Waste Form and Materials Testing Waste Form Testine - Soent fuel Work continues on the compilation of information for the Waste Form Characterization Report.
LLNL-February Status Report 3/13/91 i
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o The December 1990 report from PNL described a need_ to improve the method of preparing spent fuel grains for subsequent flow-through dissolution testing so that the small subgrain particles (those smaller than about 2 gm) will be eliminated.
.Two methods have been tried:
i
- 1) wet screening rsing a screen with 5 m openings, and
- 2) L aqueous settling-rate segregation.
The latter simply involves ultrasonic agitation and stirring to produce an aqueous sumension of particles in a beaker. After a few seconds of settling, the aqueous solution is de: anted along with the smaller particles while the larger particles settle to the bottom and remain in the beaker.
The latter method seems to work 4
somewhat better and is easier to perform in the hot cell.
Different solutions (deionized water, dilute solutions of hcl or KOH, and a mixture of deionized water and glycerol) were tried with method 2, but little difference was observed.
Therefore, in the future, deionized water (or, perhaps, dilute carbonate / bicarbonate solutions) will be used to prepare fuel-grain specimens for flew-through dissolution tests using this method.
Finished synthesizing another new batch of schoepite (- 13 g). X-ray diffraction (XRD) confirmed its purity. A sub-sample will be sent to the LLNL Chemistry Department for surface area measurement. Another sub sample will be sent to PNL.
The draft bibliography by W. McKenzie entitled "UO2 Dissolution Kinetics, Solubility, and Thermochemical Properties of Uranium: Selected References" was prepared and is being reviewed by the Waste Form Technical Area staff, A Readiness Review was completed for Activity D 20-53a, Flow Through Dissolution Tests on UO (LLNL).
2 A review of the-PNL Test Plan for Activity D-20-53b, " Flow Through Dissolution Tests on Spent Fuel" was completed. W. Gray of PNL visited LLNL on February 11 and discussed the flow-through dissolution test plan.
The calibrations and operational testing of the uranium analyzer testing were completed in preparation for initiating the UO Flow-through tests.
2 R. Einziger and L Thomas of PNL met with R. Stout at LLNL to discuss oxidation of spent fuel and work plans for the current fiscal year. Test instructions for the altered r
-scope of work were written.
Samples will be loaded into the dry baths in February /early March depending upon the final negotiated schedule.
Waste Form Testine - Glass Work continued on the preliminary Waste Form Characterization Report. A draft l
of the glass portion of the document includes the important glass-related-information in the form of tables and figures. The ANL contribution to the Waste Form Characterization Report was received and incorporated into the draft document.
The three areas examined by ANL include the effect of fracturing on glass reaction, the effect of radiation on glass reaction, and the estimation of glass
-LLNL-February Status Report 3/13/91
reaction rates under a variety of conditions. The glass reaction rates reported were based on long-term static leach tests to establish a " final" reaction rate, on vapor phase hydration reaction at-repository-relevant temperatures, and on long-term application of the unsaturated test method. Reaction rates were presented for a range of potential glasses to be produced by the Defense Waste Processing Facility (DWPF).
The N2 tests (SRL actinide-doped glass) continued as scheduled with no sampling period occurring this month. These tests have now been in progress for over five years with the anniversary date being 2/3/91.
The N3 tests (ATM-10, a West Valley actinide-doped glass) continued as scheduled.
The tests have been in progress for 182 weeks.
Work to characterize the distribution of actinides in solution has been completed at ANL, and a letter report describing the results was submitted to M. Buchholtz ten Brink at LLNL. Further exposure of the alpha bearing filtered particles to nuclear emulsion has produced separate alpha tracks that can M vectored to discrete particles which are then examined using transmission electra microscopy (TEM). The alpha tracks are produced by the Ca-Th phosphate phase described previously. Additionally, many small particles of the clay substrate which contains the Ca-Th phosphate phase were mounted for X-ray diffraction analysis.
This was a tedious procedure since the clay particles were on the order of 1 um diameter. A successful XRD pattern has been obtained at several focal lengths and the patterns are being compared to those produced using electron diffraction in the TEM. A draft journal article was submitted describing these results. The results are significant because they indicate that the ratio of Am/Pu suspended in solution to thct actually dissolved in solution is greater than 1000:1. These findings may affect the application of solubility-limit based performance assessment models and could influence the design of the engineered barrier system for radionuclide containment.
YMPO was contacted by J. O'Keefe of NASA Goddard concerning information they have about the rates of tektite dissolution in natural environments. Tektites are natural glasses that have apparently survived for millions of years on or near the surface of the earth. Experimental dissolution studies of tektites have shown that the presence of magnesium in solution suppresses the rate of tektite dissolution (commonly by a factor of 100 or more) either by poisoning the surface or due to the formation of a magnesium-rich alteration layer that inhibits transport. Plans are to examine and quantify this effect for nuclear waste glasses by including magnesium in the buffer solutions of the flow-through tests. This is part of the reason for revising the test matrix in Activity D-20-31 as described below.
Work continued on developing a test plan matrix for dissolution tests of waste glasse.s.
A reduced funding level makes it imperative that only a few key experiments be done in the remainder of this fiscal year. A reduced number of pHs, temperatures, and glass compositions will be used.
LLNL-February Status Report 3/13/91 l
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Container Materials Modeline and Testing W, Love from RMI Titanium in Brea, CA visited LLNL and gave a presentation on various aspects of titanium and titanium alloys. J. Ratka from Brush-Wellman in Cleveland, OH. visited LLNL and gave a presentation on various aspects of copper-beryllium alloys. Detailed presentations were given on all aspects of these metals as they would apply to a high level nuclear waste disposal container.
D. Macdonald, SRI International, visited LLNL on February 14 to discuss container life prediction modeling. He is developing models for the Canadian Repository Program which, with some modification, could also be applied to Yucca Mountain EBS design concepts.
Four staff members attended the Golden Gate Metals and Welding Conference held in San Mateo, CA on February 5-7.
D. McCright was a session chairman and W. Halsey presented a paper on Container Materials.
W. Clarke attended the second planning meeting in Las Vegas on February 21 for the DOE EBS Concepts Workshop.
All five sections of the degradation mode survey on Ni-Cr-Mo alloys are completed.
The sections have been reviewed for technical content. Reviewer's comments ha been incorporated into the documents. The five sections are:
1)- Introduction,
- 2) Phase stability, 3 Stress corrosion cracking and localized corrosion in chloride environments,
- 4) Corrosion in marine atmospheres and brines, and
- 5) Stress corrosion cracking in hydrogen environments.
The entire report (all five sections) will receive management and QA reviews as a single document. This is expected to occur in March.
Intecrated Radionuclide Release Discussions and document reviews were conducted for collaboratioris and work
~
plans for sorption and transport work with LANL.
A review was completed for the Individual Software Plan for the ion microscope experiments. Began testing software _ developed for calibration of the ion microscope -
to measure concentrations of trace elements in YMP samples. Completed a depth profiling analysis of uranium and thorium ion implants as part of the calibration effort.
Contmued construction of the flow-through chemical-hydrological system.
Installation and safety testing are expected to be completed in March.
Drafts of the letter report and manuscript on identification of actinide-bearing colloids in waste glass were completed.
LLNL-February Status Report 3/13/91 m.
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Reduced the inductively coupled plasma-mass spectrometer (ICP-MS) data for the Rare Earth Element standard intercalibration.
Thermodynamic Data Determination A thin window Ge detector was set up and shielded. Calibration with NIST primary efficiency standards completed the validation of the gamma counting facility. The 75 kev transition in Am243 is used to determine the oncentration of Americium in the solutions used for the spectroscopic determination cf Americium complexation constants.
Experiments to determine the _ extent of americium hydrolysis at ambient temperature continued in preparation for measurements at elevated temperatures.
Controlling the pH of the analyte solutions was found to be difficult. Anaiysis of the data afforded a value of log K(1,-1,0) = -7.53 0.59 which compares well with the value presented in the NEA draft americium review.
The optical cell in the Guided Wave variable temperature spectrometer was reconstructed.
The modification resulted.in markedly improved data.
Consequently, the first LLNL high-temperature spectroscopy experiments were conducted. Spectroscopic complexation data were collected at 25,50,75, and 95 C for the americium '..ydrolysis system. The high temperature data are important for performance assessment calculations that wii' be made at elevated temperature near-field conditions.
q In response to an OCRWM request, three contracts were initiated with U.S. scientists to provide independent technical and peer reviews of the Nuclear Energy Agencys review of actinide thermodynamic data. These contracts are as follows:
~
- 2) F. Pearson, Jr., Consultant, Peer Review, uranium
- 3) J. Sullivan, Argonne National Laboratory, Critical Technical Review, plu to'nium 1.2.2.4 Design, Fabrication, and Prototype Testing Waste Packace Desicq No significant activities.
Container Fabrication and Closure Development No significant activities.
Container / Waste Packace Interface Analvsis A draft of the Waste Package Plan Milestone 1, the EBS Mission Statement, has been released to YMP for review.
i LLNL-February Status Report 3/13/91
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The methodology for developing alternate design concepts har been internally reviewed and apprc M for implementation.
1.2/s itEGULATORY AND INSTITUTIONAL l
NRC Interaction Sut$ port No significant activities.
Site Characterization Procram No significant activities.
Technical Sut't' ort Documentation No significant activities.
Etudy.fl,an Coordinatintt Two study pit.ns were received for review from USGS.
Semi Annuni Procress Renotts No significant activities.
1.2.9 PROJECT M ANAGEM ENT 1.2.9.1 Management One presentation was given at an LLNL-YMP staff meeting:
It Bryan discussed Records Management.
The Sample Overview Committee approved LLNL specimen removal requests for Integrated Testing and Geomechanics experiments.
L. llallou participated in Early Site Sultability Evaluation meetings in Denver, February 7-8 and February 27 March 1.
Staff attended a software-QA workshop in Las Vegas on February 4-7 which provided an open fomm to identify problems with the present SQA system and to initiate development of recommendations for improvement.
D. Wilder, D. Short and other YMP statf briefed J. Bartlett in Las Vegas on February 8th on the YMP-QA Workshop. -
Staff members discussed LLNL comments with D. Helton of YMPO on the YMP Information Management Systems Plan, Software Management Plan, Data Management Plan, and Computer Resources Management plan.
P LLNL February Status Report. 3/13/91
L. Jardine presented a paper entitled "Using a System Engineering Process to Develop Engineered 13arrier Design Concepts" to toe Waste hinnagement '91 Conference in Tucson, AZ on February 25.
Two staff members attended the Records Coordinator Conference & Workshop in Las Vegas, February 5 6, which included a trip to the Yucca hiountain Records and Document Control Offlee.
i 1.
Blink was appointed as the LLNL representative to the Technical / Quality /hianagement (T/Q/ht) Group.
1.2.9.2 Project Control s
Submitted the January FTE Report and Cost Plan to YhiPO.
initiated work on preparing the following planning documents:
- 1) FY93 WAS/FWP
- 2) FY93 LLNL FWP
- 3) YhiP Performance hieasurement Baseline covering the period of October 1,1990 through October 1,2001.
A Reviewing and revising the PACS network and budget data. The FY91 budget, as compiled by the SAIC PACS system, totals approximately $2 million more than approved LLNL FY91 budget.
1.2.9.3 Quality Assurance Quality Procedures 033 YhiP-QP 2.6, Readiness Review; 033-YhiP-QP 2.9,
' Indoctrination and Training; and 033-YhiP-QP 3A Scientific Notebooks have been revised and distributed.
Draft charters for the Te<:hnical/ Quality /hianagement Group and the Software Advisory Group were reviewed, and comments were forwarded to YhiPO.
The Quality Assurance Requirements Specification for Instrument Calibration 4
Services, QARS-003, was revised and distributed.
Work is continuing on the annual Trend Analyses Report.
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LLNL-February Status Report 3/13/91
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Lawrence Livermoro National Laboratory Yi LLYhiP9103200 W 13S 1.2.9 April 5,1991 "QA: N/A" Carl Certz, Project hianager Department of Energy Yucca hiountain Project Office P.O. Box 98518 Las Vegas, Nevada 89193 8518
SUBJECT:
Yucca Mountain Project Status Report hiarch 1991 Attached is the Afarch Project Status Report for LLNL's participation in the Yucca hiountain Project, if further information is required, please contact Ell:abeth Campbell of my staff at FfS 532 7854.
Sincerely, 4d e -feslie Jardine -
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LLNL Technical Project Officer for Yh1P L))/EC/cc CC:
Distribution DISCLAIMER l
The LLNL Yucca hiountain Project cautions that any information is preliminary and subject to change as further analyses are performed or as an enlarged and l
perhaps more representative data base is accumulated.
These data and interpretations should be used accordingly.
An Ecum Oworturny Emer
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.. vuvete u v enmune isn ouisat, utovu tuiu :utta muum nus ravjet i MARCli 1991 TECHNICA; HIGlillGii'5 AND STATUS REPORT TABLE OF CONTENTS 1.2.1 Systems WBS 1.2.1.1 Management and Integration (Ballou)
WBS 1.2.1.2.4 Systems Engineering Implementation (Revelli)
WBS 1.2.1.2.6 YMP Support to MSIS (Ruffner)
Performance Analyses (Chesnut)
WBS 1.2.1.4.2 Waste Package Performance Assessment (Chesnut)
Geochemical Modeling WBS 1.2.1.4.5 Geochemical Modeling & Database Development (Wolery/ Johnson)
WBS 1.2.1.4.7 Supporting Calculations for Postclosute Performance Analyses (Carrigan) 1.2.2 Waste Packagg WBS 1.2.2.1 Management and Integration (Ballou)
Waste Package Environment (Wilder)
WBS 1.2.2.2.1 Chemical & Mineralogical Properties of the Waste Package (Wilder)
WBS 1.2.2.2.2 Hydrologic Properties of Waste Package Environment (Chesnut)
WBS 1.2.2.2.3 Mechanical Attributes of the Waste Package Environment (Blair)
WBS 1.2.2.2.4 EBS Field Tests (Lin)
Waste Form & Materials Testing (Stout / Clarke)
WBS 1.2.2.3.1.1 Waste Form Testing Spent Fuel (Stout)
WBS 1.2.2.3.1.2 Waste Form Testing - Class (Bourcier)
WBS 1.2.2.3.2 Metal Barriers (McCright)
WBS 1.2.2.3.4.1 Integrated Radionuclide Release: Tests and Models (ten Brink)
WBS 1.2.2.3.4.2 Thermodynamic Data Determination (Silva)
Engineering & Systems Analyses (Ruffner/ Clarke)
WBS 1.2.2.4.1 Waste Package Design WBS 1.2.2.4.2 Container Fabrication & Closure Development (Clarke)
WBS 1.2.2.4.3 Container / Waste Package Interface Analysis (Ruffner) 1.2.5 Reculatory and insiltutional WBS 1.2.5.2.1 NRC Interaction Support (Blink)
WBS 1.2.5.2.2 Site Characterization Program (Ballou)
WBS 1.2.5.2.4 Technical Support Documentation (Blink)
WBS 1.2.5.2.5 Study Plan Coordination (Ballou)
WBS 1.2.5.2.6 Semi Annual Progress Reports (Blink) 1.2.9 Protect Manacemem WBS 1.2.9.1.1 Management (Jardine)
WBS 1.2.9.1.4 Records Management (Bryan)
WBS 1.2.9.2 Project Control (Podobnik)
WBS 1.2.9.3 Quality Assurance (Dann)
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LAWRENCE LIVERhiORE NATIONAL LABORATORY (LLNL) j YUCCA MOUNTAIN PROJECT (YMP) STATUS REPORT I
MARCll 1991 EXECUTIVE
SUMMARY
(Items Proposed fcr Reporting in YMPO or OGD Reports) 1.2.2.3 Waste Form and Materials Testing D-20-3 Parametric Studies of WVDP and DWPF Glass Four year t>atch tests with ATM 1c and ATM 8 glasses were terminated as scheduled.
While these glasses are not representative of any glass that will be produced by DWPF or WVDP, a considerable data base exists, and the results can be applied to model validation. These tests are part of the gamma radiation glass study, and were done without radiation to provide a comparative basis. The four year period represents the longest time this glass has been reacted.
The tests were done with and without tuff wafers and with and without glass (EJ 13 water only); therefore, long term results on rock / water / glass performance are now available. Additionally, since the ATM 8 glass contains 237Np and 239Pu, some information on radionuclide distribution is also available.
The solutions were analyzed for cations, radionuclides, and anions while the distribution of radionuclides was measured between the rock and the solution and as particulate material in solution. One additional test of each type is still ongoing and is scheduled for termination at eight years.
1.2.2.2 Waste Package Environment Hydrolocie Proretties of the Waste Packace Environment The tuff fracture healing study is continuing. The silica concentration in the water condensed from the steam flowing through the aluminum sample is about the same as in the water before entering the sample. This indicates that the 20 to 50 ppm silica concentration in the water condensed from the steam that flowed through the fractured tuff sample was caused by the transportation of silica by the steam. Preliminary Scanning Electron Microscope (SEM) photos of the fracture surfaces of the tuff sample indicate that the fracture surfaces before and after the experiment are different. Further SEM studies will be conducted next month.
1.2.2.3 Waste Form and Materials Testing D-20-37: Generate Models for Release Form Glass The EQ3/6 database has been converted to a format that Gt, an alternate reaction path computer code, can use. Gt will be used both to perform verification studies of EQ3/6, and to model rock-centered flow-through experiments.
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1.2.2.4 Design, Fabrication, and Prototype Testing Container / Waste Package Interface Analysis A core team of LLNL personnel is developing preliminary concept descriptions for alternate Engineered Barrier System (EDS) designs suitable for hot / dry, cold / dry, hot / wet, and cold / wet environments.
LI.b!L-Match Status Report 2-4/5/91
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1.2.1 SYSTEhtS 1.2.1.1 hianagement and Integration Staff participated in the QA workshop follow up meeting in Denver, hiarch 14.
1.2.1.2.4 Systems Engineering implementation The tentative schedule of submission of data to the Technical Database was updated and the revised schedule was sent to YMPO for Division Director approval.
A Technical Data Information Form (TDIF) associated with the thermodynamic measurements discussed in the LLNL report, UCID 21658, "The LLNL Thermochemical Database - Revised Data and File Format for the EQ3/6 Package" by J. Delany and S. Lundeen, was submitted to YhiPO. This document reports on the structure of the GEhiBOCHS (EQ3/6) database which is one component of the YhiP Technical database and lists the species in the current version.
1.2.1.2.6 YhiP Support to htSIS Staff participated in the htSIS ESF hilssion and Functional Analysis activity in Denver, March 12-15 and in Los Alamos, hiarch 26-29.
1.2.1.4.2 Waste Package Performance Assessment Staff prepared input for the YhtP Performance Assessment Review hiceting to be held in Las Vegas, April 2 3.
An abstract by D. Chesnut entitled "The Demands Placed on Waste Package Performance Testing and hiodeling by Some General Results of Reliability Analysis" was submitted to the Focus /91 Nuclear Waste Packaging Conference to be held in Las Vegas on September 29 - October 2.
Staff participated in the ESF mission / Functional Analysis hiceting at Los Alamos, hiarch 26 29, 1.2.1.4.5 Geochemical hiodeling and Database Development Software documentation continues with the 1983 EQ3NR User Guide being revised for consistency with the recent code release (E' 3/6, Version 3245.1090). A matching Q
user guide is being prepared for the EQPT code, which is the database preprocessor for the EQ3NR and EQ6 codes. The draft EQ6 user guide is being revised to incorporate internal and external review comments.
1.2.1.4.7 Supporting Calculations for Postclosure Performance Analyses YhiP approved C. Carrigan's proposal to study seismically induced movements of the water table at and near Yucca hiountain. Internal QA grading was completed for this activity.
LLNL-hiarch Status Report 4/5/91 l
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1.2.2 WASTE PACKAGE 1.2.2.1 hianagement and Integration W. Clarke attended planning meetings on hiarch 7 at LLNL and on hiarch 14 in Las Vegas for the June 18-20 DOE EDS Concepts Workshop in Denver that was requested by the NWTRB.
1.2.2.2 Waste Package Environment The Near Field Environment Report (NFER) was QA graded using the internal LLNL procedure. LLNL hosted YhiPO staff on hiarch 7 and 8 to discuss the organization of the NFER.
Chemical and hUneralocical Pror'erties of the Wastr !, 'kane Environment Calculations have been started to estimate the effect of hydration water properties on the thermodynamic properties of clinoptilolite.
A prototype implementation has been started of the vanselow solid-solution model in EQ3/6 using the numerical solver "zbrent".
Hydrolonic Properties of the Waste Package Environment The tu" fracture healing study is continuing. The silica concentration in the water condensed from the steam flowing through the aluminum sample is about the same as in the water before entering the sample. This indicates that the 20 to 50 ppm silica concentration in the water condensed from the steam that flowed through the fractured tui, sample was caused by the transportation of silica by the steam. Preliminary Scanning Electron hilcroscope (SEhi) pitotos of the fracture surfaces of the tuff sample indicate that the fracture surfaces before and after the experiment are different. Further SEhi studies will be conducted next month.
The first draft of the revised Study Plan for the Laboratory Near-field Hydrology Task is complete.
The first draft of the Near Field Environment Report Hydrology section was completed. Work continues on a summary of this section.
An abstract by T. Buscheck, J. Nitao, and D. C'hesnut entitled 'The Impact of Episodic Nonequilibrium Fracture-hiatrix Flow on Geological Repository Performance" was submitted to the Focus /91 Nuclear Waste Packaging Conference to be held in Las Vegas on September 29 - October 2.
An abstract by W. Lin, A. Ramirez, and D. Watwood entitled " Temperature Nicasurements from a Horizontal Heater Test in G-Tunnel" was submitted to the O
Focus /91 Nuclear Waste Packaging Conference to be held in Las Vegas on September 29 - October 2.
LLNL-hiarch Status Report 4/5/91
f Staff met with LANL staff on March 4 to discuss common issues, Mechanical Attributes of the Waste Packace Environment Revised Section 3.0, Methodology, of the Study Plan for Characterization of Mechanical Attributes of the Waste Package Environment (Study Plan 8.3.4.2.4.3) incorporating the review comments received.
EBS Field Tests /ESF Test Desien W. Lin has been named Task leader for the Engineered Barrier System Field Tests.
An abstract by K. Lee, and T. Ueng entitled " Field Air injection Tests to Determine the Effect of a Heat Cycle on the Permeability of Welded Tuff" was submitted to the Focus /91 Nuclear Waste Packaging Conference to be held in Las Vegas on September 29 October 2.
1.2.2.3 Waste Form and Materials Testing Waste Form Testinn - Spent fuel Activity Plan D-20 53b " Flow Through Dissolution Tests on Spent Fuel" (at PNL) has been completed and is in final review at LLNL. Internal QA Grading was also completed for the LLNL portion of this activity.
The method developed for removing small subgrain particles from fuel grain specimens prepared for flow-through dissolution testing was expanded to include use of dilute-carbonate / bicarbonate solutions.
The UO2 dissolution tests (Activity D-20-53a) were initiated at LLNL.
Buffer solutions were prepared. The solutions are a very weak carbonate / bicarbonate at pH 10 (total C = 2x10 4M) and a very atmospheric sensitive solution at pH 8 (Total C = 2x10 2M),
LLNL approved modification of the test matrix for the dry bath oxidation tests at PNL. The revised loading diagram has been implemented.
These tests will determine grain volume oxidation rate parameters for oxidation modeling.
4 K. Pedersen has joined the spent fuel task an,d will be working on the Waste Form Characterization Report.
Comments on the paper by L. Thomas, O. Slagle and R. Einzinger, entitled
" Nonuniform Oxidation of LWR Spent Fuel in Air", were received from the editor of the Journal of Nuclear Materials and incorporated as needed. Permission to publish has been received from LLNL and YMPO, An abstract by H. Leider entitled " Estimating the Time for Dissolution of Spent Fuel Under Unconstrained Conditions" was submitted to the Focus /91 Nuclear Waste Packaging Conference to be held in Las Vegas on September 29 - October 2.
LLNL March Status Report 4/5/91
An abstract by R. Elitsinger entitled " Effects of an Oxidizing Atmosphere in a Spent Fuel Packaging Facility" was submitted to the Focus /91 Nuclear Waste Packrging Conference to be held in Las Vegas on September 29 October 2.
Waste Form Testine - Glan S. Steward of LLNL has joined the glass task and will be working on collecting and analyzing data on glass compositions and their dissolution response; as well as developing a statistically designed matrix to test effects of compositional variables by flow through controlled experiments.
New cells are being prepared for the expanded glass dissolution work. Orders have been placed for additional flow rate control pumps and connectors to perform these tests. As soon as the glassware is received, work will begin on SI-and Al doped buffer solutions. Additional laboratory space has been obtained for the expanded matrix testing.
The N2 tests (SRL actinide-doped glass) have now been in progress for 268 weeks.
The N3 tests (ATht 10, a West Valley actinide-doped glass) have been in progress for 186 weeks.
The report " Parametric Effects on Class Reaction in the Unsaturated Test hiethod" was returned to ANL from LLNL with technical comments. These comments are currently being addressed.
Four-year batch tests with AThi-1c and AThi-8 glasses were terminated as scheduled.
While these glasses are not representative of any glass that will be produced by DWPF or WVDP, a considerable database exists, and the results can be applied to model validation. These tests are part of the gamma radiation glass study, and were dora without radiation to provide a comparative basis. The four-year period represents the longest time this glass has been reacted.
The tests were done with and without tuff wafers and with and without glass (F13 water only); therefore,long term results on rock / water / glass performance are now available. Additionally, since the AThi-8 glass contains 237Np and 239Pu, some information on radionuclide distribution is also available.
The solutions were analyzed for cations, radionuclides, and anions while the distribution of radionuclides was measured between the rock and the solution and as particulate material in solution. One additional test of each type is still ongoing and is scheduled for termination at eight years.
Work is underway to begin the next set of doped-buffer flow-through glass dbolution tests. Additional cells are being fabricated and more simple glass is being prepared. An operational safety plan (OSP) was written to govern sample preparation of uranium-containing glasses. The OSP must now be approved by LLNL management.
LLNL-hiarch Status Report 4/5/91
A draft of the glass task input to the Waste Form Characterization Report has been completed. Input from ANL on (Mee aspects of glass performance (Effects of Radiation, Estimates of Glass Corrosion Rates, and Effects of Cracking) were received and incorporated into the report.
The EQ3/6 database has been converted to a format that Ct, an alternate reaction path computer code, can use. Gt will be used both to perform verification studies of EQ3/6, and to model lock centered flow through experiments.
The revised Test Plans for the LLNL Activity Plan and the N2 and N3 unsaturated tests were received from ANL and approved 'at LLNL The Activity Plan and the QA grading report for the LLNL portion of this activity are completed and are awaiting signature by LLNL-YMP management and QA.
All QA activities for the ANL contract are up to date.
Container Materials Modeling and Testing The following papers have been submitted to the Focus /91 Nuclear Waste Packaging Conference to be held in Las Vegas on September 29 - October 2.
- 1) " Candidate Container Materials for Yucca Mountain Waste Package Designs" by W. Clarke, W. Halsey and D. McCright.
- 2) " Selection Process and Quantitative Criteria for YMP Container Materials" by W. Halsey.
~
- 3) "Sdmmary of Yucca Mountain Engineered System Concepts Workshop" by W. Clarke, D. Harrison-Giesler, R. Morissette, P. Childress and A. Derusch.
- 4) " Electrochemical Polarization Measurements on Pitting Corrosion Susceptibility of Nickel Rich Alloy 825" by D. McCright and D. Fleming.
- 5) " Degradation Mode Surveys of Nickel-Chromium Molybdenum Alloys and Titanium Alloys Considered for High Level Radioactive Waste Container Materials" by C. Gdowski and D. McCright.
- 6) " Degradation Mode Surveys of YMP Site Characterization Plan Candidate Materials for High Level Radioactive Waste Container Materials" by J. Farmer and C. Gdowski.
- 7) " Stochastic Models for Predicting Pitting Corrosion Damage of HLRW Containers" by G. Henshall.
- 8) " Predicting HLRW Container Failures Due to Pitting Corrosion Using a Deterministic Approach" by C. Henshall and D. Macdonald.
- 9) " Effects of Ionizing Radiatic,n dn the Anticipated Waste Package Environment at Yucca Mountain" by D. Reed and R. Van Konynenburg.
- 10) " Corrosion of Candidate HLW Container Metals in Irradiated Air-Steam Mixtures" by D, Reed and R. Van Konynenburg.
- 11) " Gaseous Release of Carbon-14 from Spent Fuel Waste Packages in a Potential High Level Waste Repository: Why the Regulations Should be Changed" by R. Van Konynenburg.
LLNL-March Status Report 4/5/91
--.-___7
- - - - - -.. ~
Integrated Radionuclide Release t
Continued preparing the final technical data submission and records package for the tuff wafer experiments.
Continued testing of software developed for calibration of the CAMECA lon microscope to measure concentrations of trace elements in YMP samples. Features added recently include automation for acquisition and reduction of large volumes of data.
As part of the calibration effort, data reduction was completed for the depth profiling analysis of the U, Th lon implant.
Continued construction of the flow through chemical hydrological system. The pressure vessel was completed, solution delivery and collection systems were modified, and installation and safety testing begun.
Completed equipment set up and received initial training for the auto-correlation photon spectrometer. Testing with standard particles and determination of the instrument's capabilities began.
Thermodynamic Data Determination Experiments to determine the extent of americium hydrolysis at ambient temperature continued. To achieve better control of the analyte solution pH, hydroxylamine buffer solutions were prepared. These solutions are for use with the glovebox enclosed laser induced photoacoustic spectrometer.
The americium concentration of the solutions was 3x10 7M and the pH varied from 5.25 to 6.75 in 0.25 incrernents. The ionic strength of all solutions was 0.5M (NaClO4). Remote spectral interrogation of both metal and reference solutions was completed for this initial study. Data reduction and analysis were initiated.
The manuscript by J. Smith, P. Zanonato, and G. Choppin entitled "An Elevated Temperature Titration Calorimeter" was reviewed and is being submitted for journal publication.
The following abstracts were submitted to the Third International Conference on Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere, Migration, '91 to be held in Jerez de la Frontera, Spain, October 21-25:
- 1) "Speciation Calculations of Pu, Np, Am and U in J-13 Well Water: Effects of Anion Concentration and pH" by C. Palmer, R. Silva and C. Miller.
- 2) "High Temperature Measurements of Americium Hydrolysis Using Absorption and Photoacoustic Spectroscopies" by R. Russo, P. Grant, G. Klunder, P. Robouch, J. Andrews, R. Torres, H. Hall, C. Palmer and R. Silva.
- 3) " Carbonate Complexation of Tetravalent Uranium" by R. Russo, R. Silva, J. Andrews, and P. Robouch.
LLNL-March Status Report 4/5/91
1.2.2.4 Design, Fabrication, and Prototype Testing Waste Package Design No significant activities.
Container Fabrication and Closure Development A Technical Data information Form is being prepared for the B&W data.
Container / Waste Packace Interface Analysis A core team of LLNL personnel is developing preliminary concept descriptions for alternate (Engineered Darder System) EDS designs suitabic for hot / dry, cold / dry, hot / wet, and cold / wet environments.
1.2.5 REGULATORY AND INSTITUTIONAL NRC Interaction Support Staff prepared and gave presentations at the DOE NRC Technical Exchang;c on hiineral Stability and Applicability of Laboratory Data to Repository Transport Calculations held in Ims Alamos, Nhi on Atarch 20-21,1991.
D. Wilder participated in the QA Enhancement Workshop held in Dallas, TX, hiarch 26-27 for the NWTRB.
Site Characterivation Procram L. Ballou and hi. Revelli continued to support the Early Site Suitability Evaluation (ESSE) activity. Both attended the meeting in Las Vegas on February 27 hiarch 1 and participated in conference calls on hiarch 15 and 28. A preliminary guideline evaluation for Postclosure Rock Characteristics is nearly complete and will be distributed to the core team.
LLNL YhtP management signed the Interface Memorandum of Understanding (IMOU-330015) pertaining to LLNL's participation in the ESSE activity.
Technical Support Documentation No significant activities.
Study Plan Coordination Technical Review was completed for USGS YMP Study Plan 8.3.1.5.1.3, " Climatic Interpretations of Terrestrial Paleoecology".
The USGS Study Plan 8.3.1.5.2.2. " Characterization of Future Hydrology Due to Climate Changes" was received for review.
LLNL-March Status Report 9-4/5/91
Semi Annual Progress Reports Guidelines were received for assembling material for the Technical Status Report (TSR) covering October 1,1990 to March 31,1991, 1.2.9 PROJECT MANAGEMENT 1.2.9.1 Management A Technical presentation was given at an LLNL-YMP staff meeting:
D. Short discussed Design Methodology for the EDS Alternatives Study.
L. Jardine presented a paper entitled " Quality Assurance Implementation Experience in the Yucca Mountain Project, Technical Activities at Lawrence Livermore National Laboratory" on March 18 in Las Vegas for the 2nd International Waste Management Conference of the American Society for Quality Control.
Staff briefed C. Gertz and YMPO staff in Las Vegas on March 22 on potential LLNL contributions to the Engineered Barrier Systems design basis and to Site Characterization.
J. Caldwell and C. Martin from Mactec visited LLNL to get input on the problem of data submittal.
L. Jardine, D. Emerson and S. Sprague participated hosts for the YMP Open House held at NTS on March 2.
Consultants authorized by DOE /HQ visited LLNL on March 5 7 and conducted a detailed review of the LLNL backlog.
L. Zucconi resigned her position as Software Quality Manager (SQM) to accept a promotion within the LLNL Computations Department. Jim Blink assumed the responsibility of the SQM as an additional duty.
T. Quinn was appointed as the LLNL member of the YMP Software Advisory Group.
She attended the Software Quality Workshop follow up meeting in Las Vegas on March 21.
Jim Blink vas appointed as the LLNL member of the Technical Integration Group.
1.2.9.2 Project Control The February Cost Report and the February FTE Report were cubmitted to YMPO.
The FY91 Project Monthly Spend Plan was updated with new input for the spending plans from the TALs.
LLNL-March Status Report 10-4/5/91
A third contract was cotablished with an independent peer reviewer for review of the thermodynamic data on Uranium. This contuct was established to fulfill the request made by OCRWhi to support the NEA review of uranium thermodynamic data.
A new PACS account was established for work being done to evaluate the role of fractures in seismically induced movements of the water table at and near Yucca i
hiountain (WUS 1.2.1.4.7).
A new contract was established with Kaiser Engineering to provide QA support including surveillance, audit and QA Program and Quality Procedure reviews.
Completed work on the following planning documents:
- 1) FY93 WAS/FWP
- 2) FY93 LLNL FWP
- 3) YhiP Performance hicasurement Baseline covering the period of October 1,1990 through October 1,2001.
Staff members are reviewing the PACS network milestones and analyzing the impacts of constrained budgets for FY92 and FY93.
An update was submitted for the ITR Short Range Plan update.
1
- 1. 2.9.3 Quality Assurance Conducted Audit 9112, LLNL Engineering hieasurements and Analysis Section, ESD, on hiarch 18-19.
Conducted Audit 9113, LLNL Electronic Services Group, on hiarch 27 28.
Conducted a surveillance, " Status Review of SIPS, Activity Plans, TIPS. and Quality Assurance Grading for Scheduled Audits".
Distributed TIP-Yht-11, Software Configuration hianagement System.
Transmitted to YhiPO for approval the QAPP Change Notice 3.0-4.
Conducted internal QA grading meetings for Activity F20-8.5, Development of hiethods and Instrumentation: Activity F20 8.10, Technical Reviews / Peer Reviews in Support of NEA Database; and Near Field Environment Report.
Transmitted to YhfPO the revised QA Surveillance Schedule (Rev.1) for the surveillances planned for the remainder of Fiscal Year 1991.
~
Transmitted to YhiPO the revised QA Audit Schedules (Rev.1) for both internal and external audits planned for the remainder of Fiscal Year 1991.
R. Dann attended the Quality Assurance hianager meeting in Albuquerque, Nht on hiarch 5.
LLNL-hiarch Status Report 4/5/91 4
_,. _ _. _... _.. - _,, _, ~
Lawrence Livem1 ore National Laboratory LLYMP9105085 WBS 1.2.9 May 9,1991 "QA: N / A" Carl Gertz, Project Manager Department of Energy Yucca Mountain Project Office P.O. Box 98518 Las Vegas, Nevada 89193-8518
SUBJECT:
Yucca Mountain Project Status Report - April 1991 Attached is the April Project Status Report for LLNL's participation in the Yucca Mountain Project.
If further information is required, please contact Elizabeth Campbell of my staff at FTS 532-7854.
Sincerely, IwA IAslie Jardhe" LLNL Technical Project Officer for YMP N*
LJJ/EC/ec cc Distribution DISCLA.IMER The LLNL Yucca Mountain Project cautions that any information is preliminary and subject to change as further analyses are performed or as an enlarged and perhaps more representative data base is accumulated.
These data and interpretations should be used accordingly.
l M ran cttxrngryEnstyr
- Umrryct Calkvrua
- Po Bcn B00 LMvmtra Cathxne 94550 s hMturw H 5)t221100 e rwu e10-386-8339 UCU L L#M
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LAWRENCE LIVERMORE NATIONAL LABORATORY YUCCA MOUNTAIN PROJECT APRIL 1991 TEC11NICAL HIGHLIGIUS AND STATUS REPORT TABLE OF CONTENTS 1.2.1 Svstems WBS 1.2.1.1 Management and Integration (Dallou)
WBS 1.2.1.2.4 Systems Engineering implementation (Revelli)
WBS 1.2.1.2.6 YMP Support to MSIS (Ruffner)
Performance Analyses (Chesnut)
WBS 1.2.1.4.2 Waste Package Performance Assessment (Chesnut)
Geochemical Modeling WBS 1.2.1.4.5 Geochemical Modeling & Database Development (Wolery/ Johnson)
WBS 1.2.1.4.7 Supporting Calculations for Postclosure Performance Analyses (Carrigan) 112.1Vaste Package WUS 1.2.2.1 Management and Integration (Ballou)
Waste Package Environment (Wilder)
WBS 1.2.2.2.1 Chemical & Mineralogical Properties of the Waste Package (Wilder)
WBS 1.2.2.2.2 Hydrologic Properties of Waste Package Environment (Buscheck)
WBS 1.2.2.2.3 Mechanical Attributes of the Waste Package Environment (Blair)
WUS 1.2.2.2.4 EDS Field Tests (Lin)
Waste Form & Materials Testing (Stout / Clarke)
WBS 1.2.2.3.1.1 Waste Form Testing - Spent Fuel (Stout)
WBS 1.2.2.3.1.2 Waste Form Testing - Glass (Bourcier)
WBS 1.2.2.3.2 Metal Barriers (McCright)
WBS 1.2.2.3.4.1 Integrated Radionuclide Release: Tests and Models (ten Brink)
WilS 1.2.2.3.4.2 Thermodynamic Data Determination (Silva)
Engineering & Systems Analyses (Ruffner/ Clarke)
WBS 1.2.2.4.1 Waste Package Design (Ruffner)
WBS 1.2.2.4.2 Container Fabrication & Closure Development (Clarke)
WBS 1.2.2.4.3 Container / Waste Package Interface Analysis (Ruffner)
L2 5 Reculatory and institutional WUS 1.2.5.2.1 NRC Interaction Support (Blink)
WBS 1.2.5.2.2 Site Characterization Program (Ballou)
WUS 1.2.5.2.4 Technical Support Documentation (Blink)
WBS 1.2.5.2.5 Study Plan Coordination (Ballou) l WBS 1.2.5.2.6 Semi Annual Progress Reports (Blink) 1.2.9 Project Manacement WBS 1.2.9.1.1 Management (Jardine)
WBS 1.2.9.1.4 Records Management (Bryan)
WBS 1.2.9.2 Project Control (Podobnik)
WBS 1.2.9.3 Quality Assurance (Dann)
LAWRENCE LIVERMORE NATIONAL LABORATORY (LLNL)
YUCCA MOUNTAIN PROJECT (YMP) STATUS REPORT APRIL 1991 EXECUTIVE
SUMMARY
(Items Proposed for Reporting in YMPO or OGD Reports)
~
1.2.14.7 Supporting Calculations for PostAIIsure Performance Analyses Water table response calculations were completed to support a manuscript to be submitted to a refereed journal. This effort involved rewriting and carrying out additional supporting calculations 'of water table response to earthquakes. These calculations also sup wrt the paper by C. Carrigan entitled "Models of Water Table Excursions Induced ay Seismic and Volcanic Events at Yucca Mountain, Nevada" that will be presented at the Spring American Geophysical Union Meeting on May 29 in Baltimore, MD.
Work continued on the organization of the special session at AGU entitled "The Potential of Tectonism and Volcanism for Producing Significant Excursions of the Water Table". The AGU and the American Institute of Physics have expressed a desire to have a press conference on the topic of tUs session during the meeting.
1.2.2.2 Waste Package Environment '
Hydrolocic Properties of the Waste Packace Environment Work was done on integrating the various hydrological modeling studies into a
~
comprehensive conceptual and theoretical framework of the thermo-hydrological features and processes which are critical to repository performance. This theoretical framework has been developed into a graphical presentation. Requests for copies o this presentation have come from YMPO, Golder Associates, and the NRC.
1.2.2.3 Waste Fordand' Materials Testlig Waste Form Testine - Soent fuel The drybath oxidation tests at PNL continue to operate without a problem. Four samples at 195*C have been continuously monitored to determine delta (O/M). At selected O/M values, ~100 mg samples have been removed for future examination.
As of April 19, the tests have been operating for ~430 hours. Other spent fuel samples are running at 175< in concurrent tests to determine the activation energy of oxidir.ing front propagation. Ceramographic sample preparation may start as early as next week.
Waste Form Tc-stine - Glass A sample of vapor hydrated WV 50 glass was analyzed using Analytic. Electron Microscopy (AEM). The purpose of this examination was to cha acterize the Ca, Th, phosphate phase formed in the reacted layer and compare the phase with that found in the material filtered from the liquid in the N3 tests. The phase that formed in the hydrated layer matched well with brockite. This matches the phase found on the filter, which suggests that the material in solution is a result of degradation of the reacted layer rather than reprecipitation from solution.
The importance of this finding is that brockite is an americium sink, and is the source of americium l
detected in the N3 test solutions.
t
1.2.1 SYSTEMS 1.2.1.1 Management and Integration Technical and management staff prepared for the June 1991 YMPO audit of LLNL-YMP.
1.2.1.2.4 Systems Engineering implementation Two draft Change Requests are in preparation:
- 1) to create a separate WBS element to support the development / maintenance of the thermochemical (GEMBOCHS) database and
- 2) to add LLNL to WBS 1.2.1.3.4 for the assodated technical database management computer support.
^
A data dictionary for the LLNL thermochemical database was prepared and submitted to YMPO for consideration in developing the Project's Parameter Dictionary.
M. Reveill represented LLNL at the Technical Database Handbook meeting at SAIC on April 16 and participated in the Technical Data Advi::ory Group meeting in Las Vegas on April 17-18.
1.2.1.2.6 YMP Support to Management Systems Improvement Strategy LLNL staff continued to support the MSIS ESF Mission and Functional Analysis activity. On April 8-12, staff attended the MSIS meeting in Las Vegas where the issue logic diagrams and ESF test descriptions were completed. On April 16-19, staff participated in the Phase II " kickoff" meeting of the ESF Functional Analysis group in Washington, D.C.
1.2.1.4.2 Waste Package Performance Assessment Staff participated in the YMP Performance Assessment Review Meeting held in Las Vegas, April 2-3. The purpose was to present FY91 progress to date and to summarize plans for the remainder of the year. T. Buscheck presented the paper entitled "Nonequilibrium Fracture-Matrix Flow, Part I: Implications for Radionuclide Transport". J. Nitao presented the paper entitled "Noncquilibrium Fracture-Matrix Flow, Part II: Impact on Radionuclide Transport". The radionuclide transport calculations covered in J.Nitao's talk have been recently conducted with the use of LLNL's flow and transport simulator W. Bourcier presented a summary of the LLNL glass performance model.
The following paper was presented at the International High Level' Radioactive Waste (IHLRW) Conference in Las Vegas, April 29-May 2:
" Preliminary Calculations of Release Rates from Spent Fuel in a Tuff Repository" by W. O'Connell.
j i
LLNL-April Status Report 2-5/9/91
1.2.LL5 Geochemical Modeling and Database Development A user guide to satisfy the documentation requirements of NUREG-0856 is being prepared for each of the three codes in the EQ3/6 package: the FQIT data file preprocessor, the EQ3NR speciation solubility code, and the EQ6 reaction path code.
These will correspond to the software as released in Version 3245.1090. The EQIT manual is completely new, and the EQ3NR manual is a major revision of a version published in 1983. The EQ6 manual has been previously reviewed using LLNL procedures, and it is being revised in response to reviewer commamts and: code changes made after the document was submitted for review.
~
~~
Continued development of a softwarelaterface between GEMBOCHS and the GT geochemical modeling code. This project. involves collaboration with the Glass Waste Form Testing Task.
Continued restructuring of GEMBOCHS and D00UT that will facilitate g$eration of composite databases for the EQ3/6 package based on alternate suites of basis and auxiliary basis aqueous species.
Began modification of the LLNL local filing system for controlling and tracking the evolution of database software products to achieve conformance with guidelines described in TIP YM 11 (Software Configuration Management System), which was approved during March.
L2.LL7 Supporting Calculations for Postclosure Performance Analyses Water table response calculations were_c_ompleted to support.
nuscript to be
. c: m submitted to a refereed journal. This effort involved rewritig
' carrying out additional su? porting calculations of water table response to e.
.iuakes. These calculations a so support the paper by C. Carrigan entitled "Models of Water Table Excursions Induced by Seismic and Volcanic Events at Yucca Mountain, Nevada" that will be presented at the Spring American Geophysical Union Meeting on i
May 29 in Baltimore, MD. Work continued on the organization of the special I
session at AGU entitled "The Potential of Tectonism and Volcanism for Producing Significant Excursions of the Water Table". The AGU and the American Institute of Physics have expressed a desire to have a press conference on the topic of this session during the meeting.
L2.2 WASTE PACKAGE 1.2.2.1 Management and Integration Rcvised FY91 workscopes for the PNL tasks were submitted by PNL to LLNL.
Comments received from LLNL were incorporated and the revised Statement of Work (SOW) was submitted to LLNL. The SOW contains an expanded workscope for each of the three tasks corresponding to direction received from LLNL in January. The revised program deliverables, cost, and schedule will be incorporated into these tasks when funding arrives at PNL in May.
LLNL-April Status Report 5/9/91.
e Technical and management staff prepared for the June 1991 YMPO audit of LLNL-YMP.
W. Clarke participated in the DOE EDS Workshop planning meeting held in Las Vegas on April 25.
i 1.2.2.2 Waste Package Environment Chemleal and Mineralocical Pmperties of the Waste Packace Environment The new heat capacity, entropy and standard chemical potential for end member components of clinoptitolite have been given to the database group to generate a new DATA 0 and DATA 1. The effects of accounting emlicitly for water of hydration will be judged by comparing EQ3/6 results using the new data with runs made using the current data.
Hydrolocic Properties of the Waste Packace Environment The revised version of the Hydrology Chapter of the Near Field Environment Report was completed. The original version of this chapter has been modified and the first draft is about to be released as a paper by T. Buscheck, J.Nitao and D. Chesnut entitled "The Impact of Hydrology on the Engineered Barrier System of the Potential Yucca Mountain Repository Site".
Work was done on integrating the various hydrological modeling studies into a comprehensive conceptual and theoretical framework of the thermo-hydrological features and processes which are critical to repository performance. This theoretical framework has been developed into a graphical presentation. Requests for copies of this presentation have come from YMPO, Golder Associates, and the NRC.
T. Buscheck is reviewing the paper entitled "T& MSS Implementation Plan for Developing and Implementing a Method for Early Ealuation of Site Suitability".
T. Buscheck and J. Nitao are developing a modeling and site characterization strategy to support the repository license application which will be presented to the M&O contractor next month.
l T. Quinn and J. Nitao ported LLNL's flow and transport simulator to the Open Computing Facility (OCF). Performance timing tests were run on this simulator on both the OCF version as well as the version on the National Energy Research Supercomputing Center (NERSC).
The performance of the OCF and NERSC versions were found to be similar.
Because this simulator heavily utilizes the C programming language, the superior C programming environment of the OCF prompted us to set up OCF accounts for J. Nitao, T. Quinn and T. Buscheck.
LLNL-April Status Report 5/9/91
The following four papers were presented at the IHLRW Conference in Las Vegas, April 29 May 2:
" Laboratory Determined Suction Potential of Topopah Spring Tuff at High Temperatures" by W. Daily.
" Microwave Measurements of the Water Content of Bentonite" by V. Latorre.
' Theory of Matrix and Fracture Flow Regimes in Unsaturated, Fractured Porous Media" by J. Nitao.
" Variation of Permeability with Temperature in Fractured Topopah Spring Tuff Samples" by W. Lin.
W. Lin attended the Sample Overview Committee (SOC) meeting in Chicago on Apnl9.
Mechanical Attributes of the Waste Package Environment Completed a revised d' raft of Study Plan 8.3.4.2.4.3 and circulated it for internal review.
EBS Field Tests /ESF Test D,cilga The following paper was presented at the IHLRW Conference in Las Vegas, April 29 May 2:
" Yucca Mountain Near Field Environment Considerations for Engineered Barrier System Design and Perfonnance" by D. Wilder.
W. Lin attended ESF meetings in Las Vegas on April 18 (site selection), April 23 (test
~
planning package) and at NTS (Yucca Mountain) on April 11.
1.2.2.3 Waste Form and Materials Testing Waste Form Testine - Soent fuel Work continued on the Waste Form Characterization Report.
The drybath oxidation tests at PNL continue to operate without a problem. Four samples at 195'C have been continuously monitored to determine delta (O/M). At selected O/M values, ~100 mg samples have been removed for future examination.
As of April 19, the tests have been ope' rating for ~430 hours. Other spent fuel samples are running at 175'C in concurrent tests to determine the activation energy of oxidizing iront propagation. Ceramographic sample preparation may start as early as next week.
Following approval of the test plan and two technical procedures in March, a Readiness Review at PNL was completed, and experimental work on Flow Through Dissolution of Spent Fuel was started in April. Spent fuel samples of ATM 103 were obtained from the Materials Characterization Center at PNL and used to load three flow through columns for room temperature dissolution testing.
One of the columns was loaded with fuel fragments l'- 3'mm in size;.the other two columns were loaded with' individual fuel' grains (10'to 30 m in size)~ prepared by crushing and screening the fuel followed by washing to remove the very fine subgrain LLNL-April Status Report 5/9/91
particles. Dilute carbonate / bicarbonate solutions are being pumped through the columns at flow rates of about 0.2 mL/ min.
Samples of column efauent are collected periodically and analyzed for uranium. Some of the effluent samples will also be analyzed for fission products such as 187Cs and 90 r.
S In addition to the spent fuel testing, unirradiated UO2 Pellets supplied by LLNL were crushed, screened, and washed (to remove the fine powder) at PNL to produce particles in the 44 to 105 pm size range for flow through testing. A portion of this material was returned to LLNL The purpose is to provide identical test material for comparison of the slightly different flow through testing methods being employed for t1e spent fuel tests at PNL and the UO tests at LLNL 2
Several flow through cells have been loaded at LLNL with UO2 and schoepite and preliminary rates of dissolution are being obtained. A common UO sample is being 2
shared between PNL and LLNL to ensure that measurements at both laboratories are comparable.
Initial difficulties in stabilizing the dissolution solutions containing carbonate have ben resolved with the help of calculations by C. Bruton. An atmosphere containing specific concentration of CO (depending on the particular solution composition) 2 will be used hereafter.
The following two papers were presented at the IHLRW Conference in Las Vegas, April 29-May 2:
" Spent Fuel Waste Form Characteristics: Grain and Fragment Size Statistical Dependence for Oxidation Response" by R. Stout.
" Spent Fuel Waste Form Characteristics: Grain and Fragment Size Statistical Dependence for Dissolution Response" by R. Stout.
Completed peer review of ORNL report " Characteristics of Potential Repository Wastes", DOE /RW-0184 Rev. I, Vol.1.
The paper by H. Leider, S. Nguyen, R. and H. Weed entitled " Estimation of the Time for Total Dissolution of Spent Fuel Under Uncoastrained Conditions" is in internal review.
Waste Form Testine - Glass The N2 tests (SRL actinide-doped glass) continued as scheduled with rio sampling period occurring this month. These tests have now been in progress for 272 weeks.
The N3 tests (ATM-10, a West Valley actinide-doped glass) continued as scheduled.
The tests have been in progress for 190 weeks.
The approved Activity Plan controlling both sets of tests was received at ANL and is being implemented.
A sample of vapor hydrated WV 50 glass was analyzed using Analytic Electron Microscopy (AEM). The purpose of this examination was to characterize the Ca, Th, phosphate phase formed in the reacted layer and compare the phase with that found in the material filtered from the liquid in the N3 tests The phase that formed in the hydrated layer matched well with brockite. This matches the phase found on the LLNL-April Status Report 5/9/91
y e
filter, which suggests that the material in solution is a result of degradation of the reacted layer rather than reprecipitation from solution. The importance of this finding is that brockite is an americium sink, and is the source of americium detected in the N3 test solutioru.
W. Bourcier attended the Program Review for High Level Waste Technology
{
Development Activities in Washington, D.C. on April 1011. On April 9, he met with ANL personnel to discuss plans for glass model development and related glass testing.
1 W. Bourcier met with A. Barkatt-(Catholic Univ. of America), J. O'Keefe and S. Alterescu (NASA Coddard) on April 19 to discuss their experimental work on tektite dissolution behavior. Their work showed the strong effect of magnesium in slowing down the rate of dissolution of both tektite and 'n0 clear w~aste glasses. More work will be performed to determine the mechanism for the reduction in reaction rate. Some work to characterize the reacted glass surfaces from future tests may be performed at LLNL and ANL.
The following two papers were presented at the IHLRW Conference in Las Vegas, April 29-May 2:
" Disposal of Vitrified Waste in an Unsaturated Environment" by J. Bates.
" Mechanistic Interpretation of Glass Reaction: Input to Kinetic Model Development" by W. Ebert.
Abstracts were submitted to two upcoming professional meetings. The paper
" Prediction of Long-Term Release Rates of Radionuclides from Nuclear Waste Glass" was submitted to Chemistry and Migrauon Behavior of Actinides and Fission Products in the Geosphere at the Migration '91 meeting to be held in Jerez, Spain, October 28-30; the paper "Recent Progress in Model Development for Nuclear Waste Glass Dissolution" was submitted to the Focus 91 meeting on Nuclear Waste Packaging to be held in Las Vegas on September 29-October 2.
ContJner Materials Modeline and Testine A combined meeting was held on April 26 with the Performance Analyses Technical Area to discuss modeling and modeling needs.
The following three papers were presented at the IHLRW Conference in Las Vegas, April 29-May 2:
"An Electrochemical Approach to Predicting Corrosion Performance of Container Materials" by D. McCright.
" Degradation Mode Surveys of High Performance Candidate Container Materials" by G. Gdowski.
" Gaseous Release of Carbon-14: Why the High Level Waste Regulations Should be Changed" by R. Van Konynenburg.
Intentrted Radionuclide Release
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Data reduction of depth profiling analysis $f U, Th lon idplant continued as part of the calibration effort... Discrepancies in the results.were resolved..when discussions LLNL April Status Report 5/9/91
a with the laboratory that provided the implants indicated that differing implant procedures were used in some of the samples.
Received the final report " Residence Times of Radium, Thorium and Lead in J 13 Well at the Nevada Test Site" by S. Copenhaver, S. Krishnaswami, K. Tureklan, and H. Shaw and closed the subcontract with Yale University.
The following paper was presented at the IHLRW Conference in Las Vegas, April 29-May 2:
" Effects of Heterogeneity on Actinide Distribution Rates in Tuff Rock" by M. Buchholtz ten Brink, D. Phinney, and D. Smith.
4 Thermodynamic Data Determination.
The americium GID hydrolysis measurements have been completed.
A paper on the high temperature Guided Wave spectrometer and the results from the investigation of the praesodymium acetate system was presented at the ANS International Topical Conference on Methods and Applications of Radionnalytical Chemistry IL An article in The Tournal of R_.g.dioanalytical and Nucluy Chemistry
-will result from this meeting.
Praesodymium, a non radioactive stand in for americium, was used in the development stages of the high temperature spectrometer.
J. Rard submitted the selected technetium data for review by the NEA.
1.2.2.4 Design, Fabrication, and Prototype Testing Waste Packaee Desien No significant activities.
Container Fabrication and Closure Development No significant a ctivities.
C9ptainer/ Waste Package Interface Analysis Work continued on attemate EBS design concept descriptions in preparation for the DOE EBS workshop in Denver, June 1618.
1.2.5 REGULATORY AND INSTITUTIONAL NRC Interaction Support Staff members prepared for and gave a presentation on Natural Hydrothermal Analogs at the Nuclear Waste Technical Review Board meeting on Natural and Archaeological Analogs held in Reno, NV on April 16-17, 1991. The presentation reviewed the need to carry out a natural analog study, the approach to the study; and an overview of potential analog sites in the Taupo Volcanic Zone in New Zealand.
LLNL-April Status Report 5/9/91
o Site Ch,3racterization Procram Staff addressed comments made by the State of Nevada on the SCP.
LLNL continued to support the Early Site Suitability Evaluation task, participated in the April 17-18 meeting in Las Vegas, and prepared for the May 1 " Methodology Review".
Icchnical Support Documentation _
No significant activities.
Study Plan Coordl$ation "
Received LANL Study Plan 8.3.1.3.1.1 " Groundwater Chemistry Model of Yucca Mountain" for review.
Semi-Annual Proeress Reports The Progress Report (PR) covering October 1,1990 to March 31,1991 was submitted to YMPO on April 15. Clarification responses were submitted to YMPO on April 29.
1.2.9 PROJECT MANAGEMENT L2.9.1 Management Technical presentations were given at a LLNL-YMP staff meeting:
- 1) Ray Stout gave a talk on the Waste Form Characterization Report.
LLNL-YMP staff made formal presentations to the M&O staff on April 8-9.
L. Jardine and L. Yot.3er presented a proposed FY92 work scope to C. Certz and other senior YMPO :t'If members on March 22. The presentation emphasized the im7ortance of the disturbed zone to MCDS perfonnance and a strategy to develop a successful license application.
L Jardine discussed disposal of naval reactor spent fuel with INEL staff in a meeting at YMPO on April 12.
L. Jardine participated in the Strategic Princip2es Workshop on April 3-4 in Denver, CO.
I L. Jardine participated in the OCD Information Exchange with Edison Electric Institute (EED/U Waste in Las Vegas on April 10-11.
L. Jardine, D. Emerson and S. Sprague participated as hosts for the YMP Open House Tour held at NTS on April 20.
i LLNL April Status Report 5/9/91.
T. Quinn attended the first meeting of the Software Advisory Group for YMP in Las Vegas. This group, which was initiated by a YMP Software Quality Assurance Workshop recommendation earlier this year, completed its charter and prioritized its assigned tasks. Its immediate goal is to review Section 19 of the QARD and to reconunend any changes which could have an immediate impact on improving the Software Quality Assurance Plans of the Participants.
J. Blink partic pated in the QA Grading Workshop on April 2 3 and 16-19 in i
Las Vegas. He acted as Master of Ceremonics for the presentation of workshop results to M. Blanchard and D. Horton. He also participated in the action plan follow-up meetings during the last week of April.
The following two papers were presented at the IHLRW Conference in Las Vegas, April 29 May 2:
" Yucca Mountain Site Characterization Project Waste Package Plan" by D. Harrison-Geisler, L. Jardine and R. Morissette.
" Uncertainty Analysis of Preclosure Accident Doses for the Yucca Mountain Reposite,ry" by C. Ma, D. Miller, S. Zavochy and L Jardine.
1.2.9.2 Project Control Submitted the April FTE Report and the Cost Plan to YMPO. The Worker Data Report for January through March 1991 was also submitted to YMPO.
Submitted the 1993 LLNL Institutional Plan.
Reviewing PACd network milestones cnd analyzing impacts of constrained budgets for FY92 and FY93.
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Analyzing YMPO Performance Measurement Baseline and LLNL PACS database to l
determine differences and make modifications as required.
Expanding workscope descriptions of summary accounts in outyears.
1.2.9.3 Quality Assurance Conducted Internal Audit 91-09, " Performance Analyses", on April 25-26, 1
l Transmitted to YMPO the revised LLNL-YMP Qualified Suppliers List dated April 9.
Completed and distributed:
- 1) QP 033-YMP-QP 3.0, Rev. 2, " Scientific Investigation Control",
- 2) Change Notices QP 2.8-1-2," Quality Assurance Grading",
- 3) QP 2.1-2 3, " Preparation, Approval & Revision of Procedures, Requirements, Plans, Quality Assurance Program Description"
- 4) QP 3.4-2-1, " Scientific Notebooks".
QAPP Change Notice 033-YMP R 1.0-0-4, " Organization", was forwarded to YMPO for approval.
LLNL-April Status Report 5/9/91 f
p.' O Transmitted to YMPO external Aurilt Report LLNL-YMP 91-12 "LLNL Engineering Mcasurements and Analysis Section" and LLNL-YMP 91-13 "LLNL Electronic Services Group".
DOE conducted a surveillance at LLNL on April 8 - 10.
DOE conducted an Audit Scoping Meeting at LLNL on April 10-11 for a scheduled June 1991 audit. On April 22, staff membera provided M. Mitchell of YMPO with information on the status of technical activities (in house vs. contractor, QA vs.
preliminary, ongoing vs. planned). This information will be used to determine the scope of the technical portion of the June 3-7 YMPO audit of LLNL-YMP.
R. Dann attended the ASME Code Meeting in Washington on April 22-25.
11 5/9/91 LLNL-April Status Report
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