ML20154J050
| ML20154J050 | |
| Person / Time | |
|---|---|
| Issue date: | 01/09/1986 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2367, NUDOCS 8603100455 | |
| Download: ML20154J050 (35) | |
Text
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C CERTIFIED COPY DATE ISSUED: January 9, 1986 4-MINUTES OF THE COMBINED MEETING OF THE ACRS SUBCOMMITTEES ON WASTE MANAGEMENT AND METAL COMPONENTS OCTOBER 24-25, 1985, WASHINGTON, D. C.
Time and Place:
The ACRS Subcommittees on Waste Ma agement and Metal Components held a joint meeting on October 24-25, 1985 at 1717 H Street, N.W., Washington, D. C.
The meeting commr iced at 8:30 a.m. and adjourned at approximately 5:00 p.m. each day.
Purpose:
The purposes of this meeting were to review NRC's:
(1) High-level Waste Program Programmatic Overview and Approach --
Products, Activities and Schedules (2) Definition of High-Level Radioactive Wastes (SECY-85-309, dated September 17,1985)
(3) General Technical Approach to Identify Licensing Infonnation Needs -- Overview of Performance Assessment Methodologies and Issues em m n a ']~3 ]
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t) a 1985 Me2 ting (4) Final Waste Form Package Reliabil.ity Generic Technical Posi-tion (5) High-level Radwaste Form and Container Materials Research and Technical Assistance Programs s
Items 1,2 and 3 were reviewed on the first day; items 4 and 5 on the second day. The Presentation Schedule is enclosed (Attachment 1). A list of the documents distributed during the meeting is enclosed as Attendees:
(Total 78)
ACRS Members D. Moeller, Chairman, Waste Management Subcommittee P. Shewmon, Chairman, Metal Components Subcommittee H. Etherington, Member C. Mark, Member ACRS Consultants NRC Staff M. Carter R. Browning, DWM T. Kassner H. Miller, WM F. Parker M. Knapp, DWM M. Steindler T. Johnson, DWM E. Wick, DWM ACRS Staff K. Chang, DWM
- 0. Merrill J. Greene DWM E. Igne S. Grace, DWM J. McKinley S. Coplan DWM M. Libarkin D. Fehringer, DWM P. Brooks, DWM ACRS Fellows J. Wolf, ELD
- 5. Pa rry ---
G. Bricherel, RES R. Grill, RES Other:
F. Costanzi, RES 34 persons J. Philip, RES M. McNeil, RES C. Hackbarth, RES D. Tiktinsky, DWM J. Buckley, DWM T. Junglung, DWM C. Glenn, DWM W. Lilley, DWM t
em.
GNnutas/WM and MC October 24-25, 3
1985 Meeting' J. Linehan, DWM A. Elzeftawy, DWM L. Kovach DWM J. Bradbury DWM J. Voglewede CPB F. Forscher, IE J. Donnelly, IE P. Goldberg, OPE s
Many of the attendees included in the "Other" category above were also participants -- See Presentation Schedule (Attachment 1), Attendance List (Attachment 3) and the following summary and highlights of presen-tations for their names and affiliations.
Summary and Highlights of Presentation Part 1 - Waste Management I.
Introductory Remarks - D. Moeller D. Moeller made the following points regarding the first day's meeting to update the Subcommittee members and consultants on activities under way.
He also noted, however, that the NRC Staff had submitted to the Subcommittees a series of questions on which they requested the Subcommittees' responses.
1.
That the programmatic overview of the High-Level Radioactive Waste (HLW) Program would be primarily informational to update the committees on activities underway.
Conversely, the committees would be asked a series of questions on which the NRC Staff wants comments.
d m
mnetes/WM md MC October 24-25, 4
1985 Meeting 2.
The NRC Staff also wants ACRS coments on the definition of HLW, currently being proposed for publication in the Federal Register for public coment.
R'ega'rding the general technical approach in licensing a repository, 3.
specifically on the matter of the EPA Standards -- the Staff indicated that they will, in their presentations and discussions, respond to previous ACRS coments on this subject. These comments stated that the EPA Standards are overly restrictive and conse-quently compliance with them will be essentially incapable of being demonstrated. Also, that the release limits are not risk-based, and that the standards have many deficiencies and inconsistencies.
D. Moeller also indicated that additional ACRS coments on the EPA Standards would be prepared during the 307th ACRS meeting, November 7-9, 1985, for submission to the Commissioners.
II.
HLW Repository Licensing Program -- H. Miller, J. Linehan and S.
Grace H. Miller gave an introduction and overview of the Waste Management Staff's presentation, the purpose of which is to:
1.
Present an overview of HLW repository licensing program prodJcts, activities, schedules and resources to provide context for ACRS oversight 9
InMMO37/mFWJUfVctober 14-25, 5
1985 Meeting 2.
Review the general approach and strategies being taken in providing licensing guidance 3.
Review the staff approach to the definition of HLW 4.
Review the general technical approach and perforinance assess-ment methodologies (including EPA standard implementation and waste package assessments) 5.
Identify areas for future review Mr. Miller and Mr. Linehan then discussed the first two topics in considerable detail, following which they identified (1) what they believe to be the major programmatic concerns, (2) some areas where oversight might be useful/ appropriate, and (3) questions to which the NRC Staff would like the ACRS to consider responding. The presentation materials summarizing these three items are reproduced on the following three pages.
Item 2, in particular, provides a guide for future ACRS oversight of the Waste Management Program.
III. Definition of HLW -- F. Fehringer Mr. Fehringer stated that the problems requiring answers and therefore also requiring the NRC to adequately define HLW for regulatory purposes are:
1.
The current HLW definition is based on the source rather than on the hazard of a waste.
8@
9 MAJOR PROGRAMMATIC CONCERNS e
o SCHEDULE UNCERTAINTIES /CilANGES DOE MUST IDENTIFY SPECIFIC MILESTONES AND LEAD TIMES FOR CONSULTATION. (COMMISSION TESTIMONY BEFORE CON 6RESS "OUR COMMITMENT IS CONTINGENT ON DOE IDENTIFYING WHER IS NEEDED AND ARRANGING MEETINGS WITH US EARLY IN THE PL PROCESS IN SUFFICIENT TIME S0 THAT NRC COMMENTS ARE INCLj DOE PLANS AND PROGRAMS BEFORE DOE DECISIONS AND COM
(
o ABILITY TO TRACK ALL ISSUES NUMBER OF POTENTIAL LICENSING ISSUES IS ENORMOUS o ABILITY TO KEEP UP WITH DOE: RESOURCE CONSTRAINTS VS. NO MANY ISSUES MUST BE TAKEN UP AND SETTLED BEFORE SCP/SCA, GIVEN LON LEAD TIMES FOR PLANING AND PROCUREMENT OF EXPLORA QUALITY ASSURANCE - IMPLEMENTATION BEFORE SITE CHARACTERIZAT o
o TIGHTNESS OF NWPA SCHEDULES ACRS BRIEFING:
10/24/85 on
i i
1 l
j SOME AREAS WHERE OVERSIGHT MIGHT BE USFFUL/ APPROPRIATE GENERAL TECHNICAL APPROACH TO IDENTIFY LICENSING INFORMAT o
PERFORMANCE ASSESSMENT METHODOLOGIES:
O o
EPA STD. IMPLEMENTATION: PROBABILISTIC ASSESSMENTS o
PERFORMANCE ALLOCATION o
IN-SITU TESTING i
o COUPLED THERMAL TESTS o
SCALE AND DURATION OF TESTING GROUNDWATER TRAVEL TIME / DISTURBED ZONE o
WASTE PACKAGE RELIABILITY ASSESSMENT o
o HIGH-LEVEL WASTE DEFINITION i
4 MAJOR SITE SPECIFIC ISSUES IN SCP/SCA PROCESS o
ACRS BRIEFING:
10/24/85 71
b Q_UESTIONS s
ACTIVITY, DOES THE LICENSING PROGRAM APPROACH APPEA O
BE REASONABLE?
DOES THE MIX OF GUIDANCE FORMS APPEAR TO BE APPROPRIATE?
o DOES THE ALLOCATION OF RESOURCES APPEAR TO BE REASONABLE?
DGES GUIDANCE APPEAR TO BE TARGETED TO THE RIGHT ISSUES?
o DOES IT APPEAR TO BE APPROPRIATE LEVEL OF DETAIL?
L ACRS BRIEFING:
10/24/85 22
2 There is no disposal capacity available for certain " orphan" wastes.
3.
State and Federal governments do not know what wastes they are responsible for and therefore are unable to plan effectively for disposal facilities.
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4.
NRC licensing responsibilities may be affected by the classi-fication of wastes.
Mr. Fehringer then reviewed the Low-Level Radioactive Waste Policy Act, the Nuclear Waste Policy Act of 1982 (NWPA), and the Energy Reorga-nization Act of 1974 to further emphasize the complexity of the problem and the need for a " regulatory" definition of HLW.
He stated that NRC's approach for resolving the problem is, through a rulemaking, to develop a numerical definition of HLW.
The objectives of this rulemaking are:
i (1) To place the definition of HLW on a sound technical basis which relates waste classifications to waste hazards, i
(2) To define HLW in order to establish the level of State or Federal responsibilities, and to establish classes of DOE disposal facilities subject to licensing by NRC.
Minetes/WM and MC October 24-25, 10 1985 Meeting (3) The NRC Staff does not propose to require disposal of HLW in a geologic repository although the NWPA may effectively impose such a requirement.
Mr. F5hr'inger identified and discussed (1) various questions associated with a rulemaking to define HLW, (2) major issues regarding the defini-tion of HLW, (3) who will be affected by the rulemaking, and (4) what will be the effects on costs, risks and occupational radiation
, exposures, plus other related issues.
Regarding the NRC's general approach for waste classification, Mr.
Fehringer emphasized that it is not sufficient to examine the waste alone, but that a waste classification system must consider the risk of the waste after disposal in various types of facilities.
Mr. Fehringer indicated the Staff's favorable response to previous comments made by the ACRS on this topic in their letter to W. Dircks dated January 15, 1985.
IV. Technical Approach for Licensing HLW Repositories -- S. Coplan Mr. Coplan discussed each of the following areas, emphasizing the items mentioned under each heading.
(1) 10 CFR 60 - Requirements -- Performance Objectives for both Emplacement and Post Emplacement Operations
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Minutes /WM and MC October 24-25, 11 1985 Meeting (2) NRC/ DOE Licensing Responsibilities -- With emphasis on their respective roles.
(3) Performance Allocation -- Emphasized why performance goals s
should be developed and how they are needed to establish what is necessary and sufficient for Site Characterization.
(4) Modeling Strategy -- Levels of detail for NRC Staff's licens-ing assessment methodology.
(5) EPA Standard -- Emplacement and post-emplacement operations, groundwater and individual protection requirements, and NRC Staff's approach for implementation of the post-closure standards.
He also identified and discussed examples of scenarios over the next 10,000 years, their probabilities and consequences, by way of providing an explanation of NRC's understanding and interpretation of, and their consensus with, the DOE and EPA on the EPA Standards.
(6) Systematic Identification of Issues and Information Needs --
Processes used for identifying issues, technical approach to licensing guidance development, and performance objectives and performance issues during the operational period (both pre-andpost-closure).
As a back-up to Mr. Coplan's presentation, R. Hunter of Sandia Natisnal Laboratories (SNL) discussed the formation and makeup of a panal of 13
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1985 Meeting exp;rts who are reviewing, under SNL's dir:ction, the state of the art for probabilistic prediction of geologic processes and events. The
.results of this work will be used by the NRC during its evaluation of DOE's License application. Currently available techniques are adequate, but some are not probabilistic/ statistical techniques. The SNL effort is aimed at zeroing-in on a consensus method that can become part of a universally-accepted method for use in NRC regulatory processes.
The NRC Staff posed the following questions to which they would like the
~ ACRS to consider responding.
1.
Given the flexibility provided by 10 CFR 60, is the staff's position on performance allocation appropriate? Is it reason-able?
2.
Are the levels of review of DOE's license application that are proposed in the staff's Modeling Strategy Document reasonable?
3.
Is the staff's approach for implementing the EPA standard (intluding rulemaking to establish acceptable methodologies) reasonable?
4.
Is the staff's approach for identifying issues and information needs valid?
Is it a useful tool for reducing the number of significant issues that could arise late in the licensing process?
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15f85 Meeting
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V.
Generic Technical Position (GTP) - Waste Package Reliability -- T.
Johnson and E. Wick The Waste Management Subcomittee had previously reviewed and provid.ed coment's on an earlier draft of this document (Minutes of the January 17-18, 1985 Meeting of the ACRS Subcomittee on Waste Management, dated February 13,1985). This briefing was on the final version of this GTP, In Messrs. Johnson's and Wick's presentation, they reviewed the purpose, background, regulatory pt ition(approach,andcontentofreliability analysis), failure mode analysis and quantitative reliability analysis relevant to this topic. The purpose of this technical position is to provide guidance for an acceptable method of analysis for demonstrating reasonable assurance that waste designs proposed by DOE will meet the performance objectives and design criteria during the post-closure period.
VI.
_F)- utive Session During the Executive Session, the subcomittee members and consultants drafted two letters for consideration by the ACRS at its 307th meeting, November 7-9, 1985. The first letter contained additional coments on EPA Standards; the second offered coments on the definition of HLW.
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Minutes /WM and MC October 24-25, 1985 M;eting 14 Part 2 -- High-level Waste Form and Packaging Programs The purpose of this portion of the meeting was to review the research and technical assistance programs on material behavior in terms of their applicability to high-level waste (HLW) projects.
F. Costanzi, RES, presented an overview of the research programs being
. monitored in this area. The primary objectives of the program are as follows:
identify likely failure modes of HLW waste package identify environmental determinants of waste package failure identify critical tests and assumptions needed to demonstrate long-term waste package performance, and perform selective experiments to test assumptions and performance demonstration techniques F. Constanzi stated that the NRC Staff will stay abreast of Department of Eneroy (00E) decisions on waste form and overpack materials.
It is DOE's responsibility to demonstrate its choice of waste form and overpack materials, and NRC must determine if the demonstration is valid. DOE preliminary choices of materials to be used for the HLW package are listed below:
waste form - HLW glass, or spent reactor fuel overp.1ck - low carbon steel, stainless steel, high purity iron or copper (in Tuff environment) packing / backfill / seals - Bentonite, Bentonite / Basalt, or cement 9"
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Hinutes/WM and MC October 24-25 1985 Meeting waste package environment (groundwater) - Basalt, Tuff, salt or granite The foll.owing research programs were briefly described, s
Container Manufacturing Parameters This program is being performed by the Manufacturing Sciences Corporation.
Its objective is to assess the effect of manufacturing
, technique and variability in these techniques on overpack performance.
This work will determine the effects of manufacturing parameters and QC on overpack failure. Particular attention will be focused on weldments.
This project was initiated in early 1984.
Results so far have included an analysis showing that DOE must tighten its specifications on production techniques to ensure production of nonporous overpacks.
Pitting Corrosion There are two programs on p tting corrosion, one at the Brookhaven National Laboratory and one at the National Bureau of Standards. The objective of the progran being performed by the Brookhaven National Laboratory is to determine the degree of confidence in extrapolation of short-term laboratory tests of pitting corrosion rates to predictions of pitting corrosion rates over long times.
The results of this research will be used by NRC to judge DOE claims in regard to overpack failure by pitting corrosion; in particular, to permit NRC to judge DOE claims concerning pit growth rates. Deep, large pits will be artificially produced in typical HLW overpack material. The rate of corrosion within
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Minutis/WM and MC Octob:r 24-25,
1985 Meeting those pits will be treasured to assess the effect of geometry and chemistry (within the pit).
The program being performed by the National Bureau of Standards will assess the ranges of repository environmental conditions that govern initiation and rates of pitting corrosion in overpack materials. A likely cause of waste package failure in the HLW environment is pitting corrosion of the overpack. This projei:t will assess predictive tech-
.niques to establish when pitting corrosion may be a significant licens-
- ing concern. These analyses are necessary to permit NRC to judge DOE claims concerning waste package failure and the associated geologic repository source term. The results will reduce the uncertainty in NRC review of DOE prediction of overpack corrosion rates as a function of long-term changes in the waste package environment such as alkalinity of the groundwater.
There are two parts to the program:
First, statistical variations in passive current will be related to the tendency of a steel to begin pitting at some future time; and second, a study will be made of the statistics of pit depths as a function of time and repository conditions.
This program will provide an independent assessment of the stability of the process of pitting (which NRC Staff believe may be the most likely failure mode) in expected repository environments, and the effects of changes in that environment.
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Minutes /WM and MC Octob:;r 24-25 1985 Meeting Container Assessment This program, being performed by the Brookhaven National Laboratory, examined. the questions of crevice corrosion and hydrogen embrittlement in titanium alloy and carbon steel overpacks.
Experiments were per-formed to assess crevice corrosion in titanium and hydrogen uptake and its consequences on titanium overpack materials in salt and basalt repository environments. The results of this program (which has been
. phased out) were used to support NRC's contention that titanium alloys
' should not be used in the overpack for civilian high level waste.
Long-Team Performance of HLW Packaging Materials (Overpack)
This program, being performed by the Battelle's Columbus Laboratories, will examine likely overpack failure modes under expected repository conditions e.g. basalt, tuff and salt. Pates and conditions for various overpack failure modes will be observed such as, general corrosion, pitting corrosion, stress corrosion and hydrogen embrittlement. The aim of this program is to provide a basis for assessing DOE's demonstration of overpack integrity for 500-1000 years.
The NRC Staff stated that no models exist today that can predict the behavior of pit corrosion in overpack material.
It was also stated that good centrifugal cast material and its weld should be immune to stress corrosion cracking.
Long-Term Performance (Waste Form) 8
Minutes /WM and MC October 24-25 1985 Me: ting This program, being performed by Battelle's Columbus Laboratories, will assess the range of expected performance of HLW glas. and spent fuel as
- a HLW waste forms Laboratory experiments to measure leach rates of HLW glass and spent fuel under a range of expected repository conditions will b'e performed. The results will provide NRC with a basis to evaluate DOE's demonstration of compliance with the controlled release requirements of 10 CFR Part 60.
. Glass Analogue Study This program, being performed by the Argonne National Laboratory, will study the aging of HLW glass. This program will establish and verify the relationship between accelerated laboratory aging (by hydration) of waste-glass and natural glass analog (basaltic glass). The results will assess the extent to which short-tern leaching experiments of simulated waste glasses are representative of the long-term leaching of 300-10,000 year old HLW glass.
Long Term Performance (Environment)
This program, being performed by Battelle's Columbus National Laboratories, will assess the effect of overpack corrosion on the local overpack environment in basalt and tuff repositories. The program will develop and test a groundwater geochemistry model for predicting the effect of overpack corrosion products on the local waste package environment. The results will provide an assessment of the local stability of the overpack-groundwater system.
D -
1985 P Coupled Interactions This program, being performed by the Lawrence Berkeley Laboratory, wi.ll determine how the presence of the waste package affects its environment and vice versa.
This program will examine hydrothermal syst' ems as analogues to thermal perturbations generated by emplaced HLW. Many such changes are coupled, i.e., the combined effects of the changes are different from the sum of the separate parts. Such coupled interactions are difficult to study in the laboratory because the geologic environment is very complex, due to size effects and the very long time periods involved. Natural analogues of high-level waste repositories, such as geothermal systems and hydrothermal ore deposits, can be used to observe the response of the geologic environment coupled thermal, hydrologic, mechanical and chemical changes at the scale of interest for repository licensing.
It was stated during the meeting that a model of this " heat-engine" has been developed by DOE. The accuracy of the model remains to be verified.
Site Geochemistry This program, being performed by the Lawrence Berkeley Laboratory, will assess the geochemistry of repositories in basalt and tuff. The program will include performance of experiments and assessment of numerical modes of thermal alternation of host rock, ground water and packing material in basalt and tuff. The results of this program will provide
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Minutes /WM and MC Octob:r 24-25 1985 Meeting assessment of thermally-induced changes in the chemistry of groundwater / host rock / waste package system.
J. Greeves, T. Johnson and K. Chang of the Division of Waste Management (DWM) discussed the HLW materials Technical Assistance Program. They stated that their job is to review DOE's HLW programs and designs and to make sure that when a license for the HLW package is submitted. NRC has the capability to evaluate the package in order to comply with 10 CFR
.Part 60. DWM programmatic efforts have been primarily oriented toward keeping abreast of DOE activities, reviewing their work and identifying problems in the HLW package design. Workshops with NRC, DOE and its contractors are held periodically in order to provide an up-to-date status of the programs and to provide technical feedback in problem areas.
Regarding failure criteria, the NRC Staff stated that the performance objective for the containment of the waste within the waste package is that it should be substantially complete (negligible degradation) for a period of 300-1000 years.
Substantially complete is defined as not exceeding an annual release rate of one part in ten to the fifth of the radionuclide inventory calculated to be present 1000 years after permanent emplacement.
In reply to a question, the NRC Staff stated that this failure criteria for substantially complete containment of the waste within the waste package will be documented in a Staff technical position.
It was also stated that interchange of information between NRC, DOE and its contractors is difficult but a formal mechanism does exist for information exchange.
- ge+
Minutes /WM and MC October 24-25 21 -
1985 Meeting K. Chang, DWM, described the technical assistance programs listed below.
Teview of DOE Waste Package Program This pro, gram was performed by the Brookhaven National Laboratory. They reviewe'd the waste package data base for:
accuracy, reliability and applicability technical approach limitations of the testing data collection techniques, and significance of the data regarding resolution of waste package performance issues.
They also provided general technical assistance to the Division of Waste Management.
Evaluation and Compilation of DOE Waste Package Test Data This program is contracted to the National Bureau of Standards. They will review the waste package test data base for:
accuracy, reliability and applicability technical approach, and significance of the data regarding resolution of waste package issues.
In addition, they will identify additional test data required and also identify the tests to generate the data. Some experimental tests will also be performed.
Waste Package Verification Tests This program was performed by the Brookhaven National Laboratory and consisted primarily of the following:
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Minutes /WM and MC October 24-25 1985 Mesting identify types of tests needed to~ demonstrate that the waste package can meet the performance objectives of 10 CFR Part 60 determine test parameters and the ranges that will represent the waste package environment in basalt, salt and tuff repos-s itories, and identify information needs not presently in test plans that must be supplied as part of site characterization.
Effect of Repository Environment on Performance of Waste Pack-
. age / Engineered System Components This program is contracted to the Oak Ridge National Laboratory.
In this program they will perform the following:
provide a specification for a model/ methodology that will predict repository environmental parameters.
evaluate various models and provide general technical assistance.
Preparation of Engineering Analysis for HLW Packages in Geologic Repos-itories This program is contracted to the Aerospace Corp. K. Stephens, representing that organization, briefly discussed this program. This program consists of three tasks. They are as follows:
evaluation of methodology to assess long-term performance of
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waste package, fault tree / event construction to depict failures of waste package and transport of radionuclides from the waste package to repository facility and host rock, and the assessment of performance of DOE waste package design.
Minutes /WM and MC 0ci ber 24-25,
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1985 Me: ting e
The meeting was adjourned at about 4:00 p.m.
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NOTE:
A complete transcript of the meeting is on file at the NRC Public Document Poom at 1717 H St., NW., Washington, D. C. or can be obtained at cost from ACE Federal Reporter, Inc., 444 N. Capitol St., Washington, D. C. 20001, Telephone (202) 347-3700.
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1
.s ATTACWENT 1 ACRS COMBINED SUBCOMMITTEES ON WASTE MANAGEMENT AND METAL COMPONENTS OCTOBER 24-25, 1985 Presentation Schedule October 24, 1985
Purpose:
To review the Division of Waste Management's High-level Radioactive
~
Waste Program and the proposed definition of High-level Radioactive Wastes.
I.
Chairman's Opening Statements and Coments - D. W. Moeller
_ Approximate Time 8:30 - 8:45 a.m.
ACRS Role as Oversight Waste Management Advisory Comittee Need for Programatic Overview Need for Definition of HLW II. _NMSS Presentation 1.
Programmatic Overview and Approach:
Products, Activities, and Schedules 8:45 - 10:15 a.m.
J. Linehan BREAK 10:15 - 10:30 a.m.
2.
Definition of High-Level Radio-active Wastes -- D. Fehringer 10:30 - 12:00 NOON LUNCH 12:00 - 1:00 p.m.
3.
Review of General Technical Ar,proach:
1:00 - 3:00 p.m.
Performance Assessment Program Methodologies & Issues -- S. Coplan BREAK 4.
Waste Package Reliability Generic Technical Position -- T. Johnson 3:15 - 3:45 p.m.
and E. Wick 5.
Executive Session 3:45 - 5:00 p.m.
_ ADJOURN 5:00 p.m.
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g avowsm UgeFia 2
Oct. 24-25, 1985 Md,j.
October 25. 1985
)
Purpose:
behavior for use in High Level Waste (HLW) proje 1.
Chairman's Opening Statements and Coments, Approximate Time
- P.J.,Shewmon 8:30 - 8:40 a.m.
What is the scope and objectives of the projects?
Why is the project necessary, and use What problem is the project trying to solve Guidance to determine when the project will be terminated II.
RES Presentation (Research Programs)
Program overview. - F. Costanzi 8:40 - 12:30 p.m.
- 1. B7278 MSI Effects of Manufacturing (with a 15 min. break)
- 2. A3269 BNL Pitting corrosion chemistry
- 3. B6764 BCL Long Term Performance of i
Waste Package
- 4. D1146 NBS Electrochemical Predictive Techniques
- 5. A3237 BNL Container Assessment
- 6. B3046 LBL Coupled T-H-M-C Study
- 7. B3040 LBL Site Geochemistry
- 8. A2254 ANL Glass Analog Study 9.
Rock Mass Sealing LUNCH 12:30 - 1:30 p.m.
III.DWMPresentation(TechnicalAssistancePrograms)
Program Overview, T. Johnson /J. Greeves Details of Program, Kien Chang 1:30 - 2:00 p.m.
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Oct. 24-25, 1985 Mtg.
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- 2. A3167 BNL Review of Waste Package Verification Tests
- 3. A4165 Aerospace Preparation of Engineering Analysis for PLW Package
- 4. A4.171 NBS Evaluation and Compilation of Waste Package Test Data
- 5. 80288 ORNL Effects of Repository Environments BREAK 3:30 - 3:45 p.m.
IV. Executive Session 3:45 - 5:00 p.m.
V.
ADJOURN 5:00 p.m.
Time sh plus su.own includes formal presentation time b:ommittee questions and comments.
ACRS Con + acts:
Owen Merrill - 634-1413
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Elpidio Igne - 634-1413 S
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ATTACHMENT 2 PRESENTATION MATERIAL DISTRIBUTED DURING THE COMBINED MEETING OF THE ACRS SUBCOMMITTEES ON WASTE MANAGEMENT AND METAL COMPONENTS, DCTOBER 24-25, 1985 WASHINGTON, D. C.
s Part 1 1.
HLW Repository Licensing Program - H. Miller, J. Linehan and S.
Grace 2.
NRC - NUWSI Project Exploratory Shaft Design / Construction Meeting Summary -- D. Vieth, N. Stablein and J. Greenes, August 27-28, 1985 3.
WM&MCSubcommitteeMeeting(10/24-25/85) Handout for Definition of HLW (From December 19-20,1984), O. S. Merrill October 24, 1985 4
Advance Notice of Proposed Rulemaking, Definition of High-level Waste -- D. Fehringer, October 24, 1985 5.
Technical Approach for Licensing HLW Repositories -- S. Coplan 6.
Determining Probabilities of Geologic Events and Processes -- R.
Hunter, C. Mann and R. Cranwell (to accompany item 5) 7.
Generic Technical Position -- Waste Package Reliability Analysis.
E. Wick 8.
Letter to R. Browning, NRC, from R. Stein, DOE, dated February 23, 1985 (To accompany item 7) 9.
NUREG/CR-2808, Waste Package Reliability, C. Sastre, C. Pescatore and T. Sullivan, October 1984 (to accompany item 7) 10.
USNRC Generic Technical Position, Waste Package Reliability Analy-sis, Engineering Branch, Division of Waste Management August 1985 (to accompany item 7)
Part 2 11.
Review of Selected Research Projects on Waste Fom/ Waste Packaging (Nocoversheet--startswithsheetentitled" Objectives")
12.
Overview of HLW Materials TA (Technical Assistance) Program.
Division of Waste Management 13.
10 CFR Part 60.10. Site Characterization (Under Subpart 8 --
Licenses, Preapplication Review). Selected pages between pages 569 and 593.
14.
Figures 5.1, 5.2, 5.3 -- Reference Waste Package Conceptual Designs in Basalt, Salt, and Tuff, respectively; and Table 5.1, Comparison of Some Waste Package Parameters for the Reference Conceptual Designs
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